ML20154D561
| ML20154D561 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 10/05/1998 |
| From: | Curley V NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9810070266 | |
| Download: ML20154D561 (850) | |
Text
{{#Wiki_filter:. 1 I Oc':obe,t 5 / </ y ( NOTE TO: NRC DOCUMENT CONTRCL DESK MAIL STOP 0-5-D-24 FROM: da$ bOR , LICENSING ASSISTANT OPERgIt'iGLICEN3 BRANCH _ REGION I
SUBJECT:
OPERATOR LICENSING EXAMINATION ADMINIS ERED ON AnaasY I1- 2I 19' Vf, AT 8e nk a baUe 1, A DOCKkTNO.goh/A [ ON NnerosfI7- 2t 199f/ OPERATOR LICENSING EXAMINATIONS WERE ADMINISTERED ATTHI REFERENCED FACILITY. ATTACHED YOU WILL FIND THE FOLLOWING INFORMATION FOR PROCESSING 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 RIDS CODE A070. Item #2 EXAMINATION REPORT WITH THE AS GIVEN WRITTEN EXAMINATION ATTACHED, DESIGNATED FOR DISTRIBUTION UNDER RIDS CODE IE42. Nk AD d2 ) V
RTL #AS.640U BEAVER VALLEY JOB PERFORMANCE MEASURE EVALUATOR COVER SHEET JPM Number: 2CR-581 Rev: la System #: 004 JPM Title.- Perform Manual Makeup to Charging Suction K/A
Reference:
004020A4.01 3.8/3.3 Task ID #:0040250101 004A4.07 3.4/3.7 Rev.1 JPM Application: X Requal X Initial Exam OTraining Evaluation Method LOCATION TYPE O Perform O Plant Site O Training O Simulate O Simulator O Annual Requal. Exam O Classroom O OJT O Initial operator Exam Administered By: O Other: O Bv-T O NRC 0 Other: Evaluation Results Performer: Name: Employee No: Results O SAT Time (minutes) O) O UNSAT* Allotted: 15 Actual: Time Critical: O yes x No Administrative JPM O Faulted X
- Comments (Required for UNSAT Evaluation):
Evaluation Results O Check here if same as above Observer 1: Name: Employee No: Observer 2: Name Employee No: Obsorver 3: Name Employee No: Observer 4: Name Employee No: Time (minutes) Results Question ID Allotted Actual SAT UNSAT* Question #1 O O E%ployee No: Question #2 O O Employee No: b
- Comments (Required for UNSAT Evaluation): /
\- Evaluator (Prin : Organization: Evaluator Signatare Date:
. - _ - . ~ _ . _ __ _.. _ , _ _ . -
_ _ . .. _ _ . . _ _ . - _ __ __ _ _~ j RIL #AS.635.J BEAVER. VALLEY JOB PERFORMANCE MEASURE l EVALUATOR DIRECTION SHEET
/ JPM NUMBER: 2CR-581 sg JPM TITLE: Perform Manual Makeup to Charging suction A ** VCT level is increased to approximately 42%
and makeup flow s stopped. RECOMMENDED STARTING LOCATION: CONTROL ROOM DIRECTIONS: You are to simulate (perform) the task Perform Manual Makeup to Charging Suction. INIT. CONDITIONS: The plant is in Mode 1. RCS boron
- concentration is 720 ppm. Boric acid tank concentration is 7200 ppm. The automatic control circuitry of the Reactor Makeup Control System is maintaining VCT level at 22%. Reactor Makeup Control is in AUTOMATIC, but ar. investigation into the Reactor Makeup Control System is in (y--)/. progress. I&C requests that VCT level be l raised to 42% as part of their i troubleshooting efforts. All procedural Initial Conditions are satisfied. ;
INIT. CUE: Your supervisor directs you to increase VCT level to 42% at 75 gpm by performing a i Manual Makeup to the VCT. i
REFERENCES:
20M-7.4.N Issue 4 Revision 3 TOOLS: None HANDOUT: 2OM-7.4.N [ l (_J
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RTL #A5.635.J l l l NUMBER TITLE l.O 2CR-581- Perform Manual Makeup to Charging Suction STEP- STANDARD (Indicate "S" for Sat. or "U" ' l ("C" denotes critical step) for Unsat.). Start time: EVALUATOR NOTE: Only provide cues if simulating performance of this task. Simulator Setup IC-l'8. Verify VCT level B at 22%. CLF VLV BAT 10, 1, 0, D.
- To fail 2CHS-FCV113A Closed. Reset totalizer thumbwheels to zero. Place 7200 PPM on BB Placard 7 g ,i
- 1. Obtain a copy of 20M- -1. Candidate locates 7.4.N " Blender Manual procedure.
Makeup Operations". COMMENTS:
- 2. Obtain the RCS boron 2. Candidate obtains the concentration, latest RCS boron l
concentration. COMMENTS: 9 LUATO3 CUE: The current-aCS boron concentration is l 720 ppm. 4 Page 1 of 9 Revision la [>
RTL #A5.635.J NUMBER TITLE
;q \ ') 2CR-581 Perform Manual Makeup to Charging Suction STEP STANDARD (Indicate "S" for Sat. or "U"
("C" denotes critical step) for Unsat.) EVALUATOR NOTE: Candidate may perform calculations for B.A. flow setpoint and required volumes prior to board manipulation.
- 3. Place the " Boric Acid 3. Candidate:
Makeup Blender Control" x to STOP position. (BB- 3.1 Locates control switch A) and places switch in the STOP position. (~'s 3.2 Verifies makeup (_). control green light energizes. EVALUATOR CUE: Switch in
, STOP position. Makeup control green light energizes.
COMMENTS: i f~'h U~] Page 2 of 9 Revision la
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l RTL #A5.635.J l l t NUMBER TITLE
' 2CR-581 Perform Manual Makeup to Charging Suction )
I l STEP STANDARD l (Indicate "S" for Sat. or "U" l ("C" denotes critical step) for Unsat.) i l 4.C. Places " Mode Selector" 4.0 Candidate locates ! switch'to MANUAL. switch and places l switch into MANUAL. l COMMENTS: , 1 EVALUATOR CUE: Switch in , Manual. l O}
\ ./
s 5.C Set Total Makeup from Blender Flow Totalizer 5.C Candidate locates Total Makeup from l [for 320 gallons). Blender Flow Totalizer and adjusts counter [to at least 320 , gallons]. ( I , l ! COMMENTS: l I j i ti Page 3 of 9 Revision la l
_ . _ _._ _ . __ . . _ -. . . _ _._ .. _ _ m.... _ __ . _ . . . . _ . . _ _ . _ . . _ _ . . . _ _ . . _ . . _ . . _ . . - RTL #AS.635.J l NUMBER TITLE 2CR-581 Perform Manual' Makeup to Charging Suction STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.) t 6.C Adjust joric Acid to 6. Candidate: Boric Acid Blender" [2CH5*FCV113A] for 6.1.C Calculates boric acid desired concentration. flow (720 ppm x 75 gpm (BB-A) / 7200 ppm) = 7.5 gpm. 6.2 Dial pot turns (7.5 9Pm/4) . i
^
6.3.C Locates flow controller and adjusts controller to approx. 188 units. (i.2 l O'j units). l l I COMMENTS: l 7.C Adjust [2CHS* HIC 168), 7.1.C Candidate ca'lculates l Blender Total Flow Auto Pot Set. = 75/16 = 4.68 l Setpoint, to the or 468 Units l blender total flow of 75 gpm ( COMMENTS: i l l l i f g I Page 4 of 9 Revision la l l . ; 1
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) NUMBER TITLE i 2CR-581 Perform Manual Makeup to Charging Suction l
l STEF STANDARD l (Indicate "S" for Sat. or "U" l ("C" denotes critical step) for Unsat.) P 8.C Adjust " Primary Grade 8.C Candidate locates ~
- l. Water to Boric Acid controller and adjusts i l Blender" [2CHS*FCV114A] controller to i to the same value as approximately 75 gpm,
[2CHS* HIC 168) of 75 468 units (i 2 units). gpm. ,
~
COMMENTS: 9.C Set Boric Acid Flow to 9.C Candidate sets the l Blender Flow Totalizer Boric Acid Flow to for the total volume of Blender Flow Totalizer l boric acid to be added, at his/her discretion. 1 7.5 x ~ 320 =at least 32 75 ) l COMMENTS: O O. Page 5 of 9 Revision la 1 l
RTL #A5.635.J 1 NUMBER TITLE , .O- 2CR-581 Perform Manual Makeup to Charging Suction 1 i STEP STANDARD ' l (Indicate "S" for Sat. or "U" ' ("C" denotes critical step) for Unsat.)
- 10. Verify the inservice 10. Candidate verifies I Boric Acid Transfer inservice BATP is !
Pump is in AUTO. (BB-A) selected for AUTO l operation. l
. l COMMENTS:
11.C Open Boric Acid Blender 11. Candidate:
"w y,f Disch to Charging Pumps '
g,j [2CHS*FCV113B]. (BB-A) 11.'1 Locates control switch for 2CHS*FCV113B. 11.2.C Place control switch to OPEN. 11.3 Verifies valve red light energized. EVALUATOR CUE: 2CHS*FCV113Bl , red light energized. l COMMENTS: Page 6 of 9 Revision la
. i RTL #AS.635.J s NUMBER TITLE k 2CR-581 Perform Manual Makeup to Charging Suction STEP STANDARD (Indicate "S" for Sat, or "U"
("C" denotes' critical step) for Unsat.) . 12.C Places " Boric Acid 12.C Candidate places Makeup Control Switch" " Boric Acid Makeup , to START. (BB-A) Control Switch" to l
' START. 1 EVALUATOR CUE: Switch in START position. Makeup ;
control red light i energized. Inservice BA ) pump red light energized. j COMMENTS: , l l EVALUATOR NOTE: This is a l FAULTED JPM. No boric acid l flow will occur during l subsequent steps. i l J iO I [ Page 7 of 9 , Revision la I
.RTL #A5.635.J NUMBER TITLE
(\ ~ =. 2CR-581 Perform Manual Makeup to Charging Suction STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.)
- 13. Verify proper system 13. Candidate verifies:
response. 13.1 Boric Acid Transfer Pump in Auto AND running. (BB-A) 13.2 Proper Boric Acid Flow on recorder (2CHS-FR-113). 13.3 Proper Total M/U Flow
~). From Blender on recorder (2CHS-FR113).
g j (VB-A) EVALUATOR CUE: 2CHS*FCV113A green light energized (valve closed). 2CHS*FCV114A red and green lights energized (valve throttled). Selected Boric Acid Transfer Pump red
. light energizes. After several seconds or when asked, inform candidate Boric Acid flow is approx.
O gpm and Total flow is approximately 75 gpm. . COMMENTS: 'k Page 8 of 9 Revision la
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- 2CR-581 Perform Manual Makeup to Charging Suction g
l l' STEP STANDARD (Indicate "S" for Sat. or "U" (' ("C" denotes critical step) for Unsat.) i I i 14.C . Candidate recognizes 14. Candidate: the dilution in progress and places 14.1 Recognizes that boric ! Boric Acid Makeup acid flow is zero gpm. t Control Switch to STOP. ! 14.2.C Candidate manually stops makeup prior to reaching 42% VCT , level. I i EVALUATOR CUE: Green light l' energizes. l-[ COMMENTS: EVALUATOR CUE: I&C will I investigate the problem with 2CHS*FCV113A. It is ' not necessary to set up for Auto Makeup. (Use cue if i candidate requests j guidance.) i
~$.ALUATOR NOTE: Evaluator L should terminate JPM at j
this point. Stop Time: Page 9 of 9 Revision la
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RTL #AS.635.J BVPS JOB PERFORMANCE MEASURE - I ORAL QUESTION #1 The plant'is operating at 100% power, all systems in NSA. VCT level transmitter 2CHS*LT115 fails to 100% level indication. With no operator action, briefly explain the effect this will thave-on VCT level control. I ANSWER: VCT level control valves 2CHS*LCV112 and 2CHS*LCV115 will both go to full divert to BRS. Actual VCT level will begin dropping. ; l With no operator action, the VCT will empty since AUTO makeup is controlled by l 2CHS*LT115. AUTO swapping of the charging pump suction to the RWST will not occur since the logic is 2/2 < 5% level. TIME 3 minutes ALLOTTED.
. KSA-#: 004A3.09 3.3/3.2 Rev. 1 004010A3.05 3.3/3.2 1 R
k s/)- m REF: 2OM-7.5 figure 7-51 VCT Level Control issue 4 rev. O page 1 COMMENTS: , 1-l l' !O) I
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RTL #AS.635.J BVPS JOB PERFORMANCE MEASURE ORAL QUESTION #2 The plant is operating at 100% power, all systems in NSA. Chemistry contacts you and requests Mixed bed Os demineralizer[2CHS*DEMIN21B) be placed into service, and Mixed bed demineralizer[2CUS*DEMIN21A) be removed from service. Mixed bed demineralizer[2CHS*DEMIN21B] has been charged with new resin. What are the potential reactivity affects associated with this evolution? How are they minimized? l ANSWER: An insertion of positive reactivity is possible due to absorption of boron in the bed. Minimized by boron saturating the new' resin PRIOR to opening the outlet effluent valve. [ Purging the bed through the sample line). TIME 2 minutes ALLOTTED: , l I KSA #: 004A2.32 3.4/3.9 Rev.1 l - 004020A2.13 3.4/3.9 i T) REF: 2OM-7.4.AM.II P&L B, issue 4 rev. 4 l 20M-7.4.AM.IV.A.4 p 2 of 15 issue 4 rev. 4 COMMENTS: i l l l i Q f i l
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l.
- RTL #AS.635.J l
*
- THIS SHEET TO BE GIVEN TO CANDIDATE *
- BVPS JOB PERFORMANCE MEASURE ORAL QUESTION #2 -
l l- The plant is operating at 100% power, all systems in NSA. Chemistry contacts you and requests Mixed bed demineralizer[2CHS*DEMIN21B] be placed into service, and Mixed bed demineralizer[2CHS*DEMIN21A] be removed from service. Mixed bed demineralizer[2CHS*DEMIN21B] has been charged with new resin. What are the potential reactivity affects associated with this
- evolution? How are they minimized?
m i I i t e f.
.=
l- RTL'#A5.'635.J , P 'i~
*
- THIS SHEET TO BE GIVEN TO CANDIDATE * * :
i BVPS JOB PERFORMANCE MEASURE I ORAL QUESTION #1 l The plant is operating at 100% power, all systems in NSA. VCT j l level transmitter 2CHS*LT115 fails to 100% level indication. With no operator action, briefly explain the effect this will have on VCT level control. , l i. h I.- 4 i l' i~ l l l - i l ~. l. i i n
)
t f l: i e l l l
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RTL #AS.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE CANDIDATE DIRECTION SHEET l
- THIS SHEET O BE GIVEN TO CANDIDATE
- Read:
4 Task: lPerformManualMakeuptoChargingSuction 1 l INITIAL CONDITIONS: The plant is in Mode 1. RCS boron l concentration is 720 ppm. Boric acid l tank concentration is 7200 ppm. The l automatic control circuitry of the ) l Reactor Makeup Control System is maintaining VCT level at 22%. Reactor
- Makeup Control is in AUTOMATIC, but an
! investigation into the Reactor Makeup ! Control System is in progress. I&C l requests that VCT level be raised to 42% ' as part of their troubleshooting efforts. All procedural Initial Conditions are satisfied. Your supervisor directs you to increase VCT level l INIT. CUE: to 42% at 75 gpm by performing a Manual Makeup to l
\ the VCT. l At this time, ask the evaluator any questions you have on this JPM.
When satisfied that you understand the assigned task, announce "I am now beginning the JPM". l Simulate performance or perform as directed the required task. ! Point to any indicator or component you verify or check and announce your observations. After determining the Task has been met, announce "I have completed the JPM". Then hand back this sheet to the evaluator. l' l i if 'V l i l I
l 1 l RTL #AS.6400 BEAVER VALLEY JOB PERFORMANCE MEASURE j EVALUATOR COVER SHEET 1 l JPM Number: 2dR-NPZR Rev: O System #: 011 i i JPM
Title:
Respond to Plant Annunciators l 1 i j K/A
Reference:
011A2.11 3.4/3.6 Task. ID #:011BBB0101 j JPM Application: EU Requal X Initial Exam Training l \ j Evaluation Method LOCATION TYPE l [ Perform Plant Site Training Simulate Simulator Annual Requal. Exam Classroom OJT j l Initial Operator Exam f Administered By: Other: l l [] BV-T l NRC l Other: i I } Evaluation Results t l Performer: Name: Employee.No: f Results [3 SAT Time (minutes) UNSAT* Allotted: 15 Actual: f X
- Time Critical: Yes No j
! Administrative JPM [3 Faulted
- Comments (Required for UNSAT Evaluation):
i i Evaluation Results Check here if same as above i Observer 1: Name: Employee No: Observer 2: Name Employee No: Observer 3: Name Employee No: l Observer 4: Name Employee No: } Time (minutes) Results Question ID Allotted Actual SAT UNSAT* l. i { Question #1
- Employee No:
Question #2 [3. Employee No: i
- Comments (Required for UNSAT Evaluation):
i l - 4 Evaluator (Print): Organization: f Date: j Evaluator Signature ,
>- 1 RIL #AS.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE-
. EVALUATOR DIRECTION SHEET f
JPM NUMBER: 2CR-NPZR JPM TITLE: Respond to Plant Annunciators TASK STAN.: PZR level transmitter 461 is contr.olling PZR level in automatic.. RECOMMENDED STARTING LOCATION: CONTROL ROOM DIRECTIONS: You are to simulate (perform) the task Respond to Plant Annunciators INIT. CONDITIONS: The plant is in Mode 1. All systems are in NSA. O You are the Reactor operator, and you are to respond to any annunciators received.
REFERENCES:
20M-6.4.IF issue 4 rev. 4 TOOLS: None HANDOUT: 20M-6.4.IF issue 4 rev. 4
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RTL #A5.635.J (: NUMBER TITLE 2CR-NPZR Respond to Plant Annunciators 1 l STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.) Start time: INSTRUCTOR SETUP Init 18 Insert XMT RCS19 1 0,0,0,D EVALUATOR NOTE: The candidate may.first respond to individual ARPs before eventually recognizing the
% j. symptoms for entry into l 20M-6.4.IF.
Candidate locates . procedure 20M-6.4.IF. i l
- 1. Candidate identifies a 1. Candidate identifies level channel has level channel failed. [2RCS*LT459) has failed and refers to Attachment 1 .
COMMENTS: I l' i; + i i Page 1 of 9 Revision 0
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l RTL #AS.635.J l
.O NUMBER TITLE 2CR-NPZR Respond to Plant Annunciators i
STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.)
- 2. Candidate identifies 2. Candidate identifies ~~
which level channel has level channel i failed, and how it has (2RCS*LT459] has failed. failed, it has failed low. COMMENTS: 'li 3.C Place PRZR Level 3.C Candidate-places PRZR control Channel Level control Channel selector switch to II & selector switch to II . III position. & III position. COMMENTS: i
- 4. Ensure PRZR level 4. Candidate places recorder is selected to PRZR level recorder j controlling channel, channel III.
l COMMENTS: , 1 I t l' !O Page 2 of 9 Revision 0
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j~ . l' RTL #AS.635.J ( NUMBER TITLE 2CR-NPZR Respond to Plant Annunciators f l STEP STANDARD (Indicate "S" for Sat. or "U" for Unsat.) (. ("C" denotes. critical step) , A S. Ensure adequate Makeup 5. Candidate checks to VCT blender set in t automatic. 1 L COMMENTS: L
- 6. Ensure PZR Heaters 6.1 Candidate checks to return to normal ensure PZR Heaters operation. return to normal i operation.
i l I COMMENTS: i. !' EVALUATOR CUE: As your supervisor, I desire heater groups D, and C to be energized. r l l t I-i, r I
\ l i
Page 3 of 9 Revision 0 i I i
_. . _ - 1 , . . . . . . - _. _.._._.._..__ __.. _._ _ __. _. . . _ . _ . . _ _ _ _ . RTL #A5.635.J. . (s ' A). l NUMBER- TITLE i 2CR-NPZR Respond to Plant Annunciators , STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.) 6.2 Candidate places CS for heater groups D t and C to CLOSE Verifies red' lights LIT , i Verifies green lights NOT LIT O COMMENTS: ; 1 1
- 7. Ensure [2CHS*FCV122] is _7 . Candidate checks repositioned to desired [2CHS*FCV122] is setpoint. repositioned to desired setpoint.
I COMMENTS: 1 i l I 1 l 1 i J i l !' Page 4 of 9 Revision 0 l.
l L RTL #AS.635.J [ NUMBER TITLE l~ J 2CR-NPZR Respond to Plant' Annunciators i STEP STANDARD I (Indicate "S" for Sat. or "U"- ("C" denotes critical step) for Unsat.) 8.C Restore letdown 8.1.C Candidate places A/M station for Charging pump disch. Flow control Vlv (2CHS*FCV122) to *;AN (BB-A) Verifies MAN light LIT Verifies AUTO light t NOT LIT i
\_
COMMENTS: . 8.2.C Candidate adjusts position of Charging L pump disch. Flow control Vlv (2CHS*FCV122] to achieve 30-50 gpm as indicated on (2CHS-FI122A) (VB-A) ] COMMENTS: l l 1 l
-t
- 'q.)
l Page 5 of 9 Revision 0
.RTL #AS.635.J.
[ NUMBER TITLE
~2CR-NPZR Respond to Plant Annunciators STEP STANDARD (Indicate "S" for Sat, or "U"
("C" denotes critical step) for Unsat.) 8.3 Candidate checks Letdown orifices 21, 23, & 22 isol (2CHS*AOV200A,B,& C) CLOSED Verifies green light LIT o Verifies red light NOT LIT v COMMENTS: 8.4.C Candidate places CS for Regenerative Heat Exch Letdown Inlet Vlv[2CHS*LCV460A) to OPEN (BB-B) Verifies red light LIT Verifies green light NOT LIT COMMENTS: O Page 6 of 9 Revision 0
f' RTL #AS.635.J ("') N,s.
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NUMBER TITLE r- , j 2CR-NPZR Respond to Plant Annunciators i I STEP STANDARD L (Indicate "S" for Sat. or "U" , ("C" denotes critical step) for Unsat.) 1 i 8.5.C Candidate places Non- I Regenerative HX Disch. l Press Control Vlv i [2CHS*PCV145] A/M I station to MAN and l l adjusts to 50% demand. l ! 1 Verifies MAN light LIT I' ( Verifies AUTO light i ! NOT LIT Uses raise lower PB to adjust demand-to 50% COMMENTS: i
- EVALUATOR CUE
- As your j supervisor, I desire a 60 gpm and a 45 gpm orifice to be placed in service at this time, o .
l I i i~ i - l Page 7 of 9 Revision 0 l J
l RTL #AS.635.J l'. NUMBER TITLE p. i
- j. 2CR-NPZR Respond to Plant Annunciators l-l \
I ' t . 1 STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.) . 8.6.C Candidate places CS for Letdown orifices I 21, 23 or 22, isol l [2CHS*AOV200A&BorC) to l OPEN l l i Verifies red lights l l LIT l i Verifies green light O NOT LIT LU l COMMENTS: . l l I' 8.7. Candidate adjusts Non-Regenerative HX Disch. Press Control Vlv [2CHS*PCV145] A/M. station to achieve-a backpressure of 260 psig as indicated on [2CHS*PI145] (BB-A) L COMMENTS: O ( Page 8 of 9 Revision 0
1
. 1 RTL #AS.635.J O NUMBER TITLE l f
2CR-NPZR Respond to Plant Annunciators 1 i. l I l STEP- STANDARD l (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.) 8.8.C Candidate places Non- ! j Regenerative HX Disch. Press Control Vlv [2CHS*PCV145) A/M station to AUTO. l l COMMENTS: l O)
\- EVALUATOR CUE: For the purposes of this JPM it is
! NOT necessary to refer to Tech Specs or initiate an - MWR. Candidate should indicate the need to manually control Charging l pump disch. Flow control Vlv [2CHS*FCV122] to restore PZR level to setpoint. L COMMENTS: I I l Stop Time: f O Page 9 of 9 Revision 0 l i
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RTL #AS.635.J BVPS JOB PERFORMANCE MEASURE ( ORAL QUESTION #1 Using the PZR level Hot and Cold calibration curves, explain why it is necessary to have Hot and Cold Channels, as opposed to having one transmitter calibrated for the full range of temperature and pressure. ANSWER: Necessary to have two since with only one, the . large density change over the spectrum of cold atmospheric pressure to hot full power pressure would leave areas of the transmitter with large inaccuracies. TIME S minutes ALLOTTED: KSA #: 011 K4.03 2.9
/
REF: Pressurizer Tank Curves of Tank Curve Book. Rev. 0
- COMMENTS:
0 4
- N) b
RTL #AS.635.J BVPS JOB PERFORMANCE MEASURE () ORAL QUESTION #2 The plant is operating at HZP Mode 3 with PZR level control in 4 Manual. PZR level channel 461 is reading 50%. How will indicated PZR level respond to a leak in the reference leg that slowly empties the reference leg? Explain. ANSWER: Indicated level will slowly rise. Transmitters are calibrated such that when AP is zero, the pressurizer indicates full. Since the reference leg is the high side pressure, as the - leak empties reference leg AP will drop and indicated level will rise TIME 4 minutes ALLOTTED: KSA #: 028 AK1.01 3.1
-~g .
}
/ REF: Theory
( COMMENTS: O
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RTL #A5.635.J 1 I *
- THIS SHEET TO'BE GIVEN TO CANDIDATE *
- l l
l BVPS JOB PERFORMANCE MEASURE ORAL QUESTION #2 ; The plant is operating at HZP Mode 3 with PZR level control in l Manual. PZR level channel 461 is reading 50%. How will indicated PZR level respond to a leak in the reference leg that slowly empties the reference leg? Explain. i e f l l i l I I I 4 J i O i J f
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- THIS SHEET TO BE GIVEN TO CANDIDATE * ,
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BVPS JOB PERFORMANCE MEASURE ! ORAL QUESTION #1 Using the PZR-level Hot and Cold calibration curves, explain l
- why it is necessary to liave Hot and Cold Channels, as opposed l to having one transmitter calibrated for the full range of temperature and pressure.
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RTL #AS.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE
- [] CANDIDATE DIRECTION SHEET V
- THIS SHEET TO BE GIVEN TO CANDIDATE
- Read:
l Task: lRespondtoPlantAnnunciators l l INITIAL CONDITIONS: The plant is in Mode 1. All systems are ; in NSA. i i INIT. CUE: You are the Reactor operator, and you are to l respond to any annunciators received. At this time, ask the evaluator any questions you have on this JPM. l , When satisfied that you understand the assigned task, announce ~
)
"I am now beginning the JPM".
l Simulate performance or perform as directed the required task. Point to any indicator or component you verify or check and l announce your observations. l [ After determining the Task has been met, announce "I have ' completed the JPM". Then hand back this sheet to the evaluator. l l t ? 5
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i i . j RTL #AS.640U BEAVER VALLEY JOB PERFORMANCE MEASURE ! EVALUATOR COVER SHEET ) JPM Number: 2CR-529 Rev: 2a Systet #: 006 JPM
Title:
Transfer to Cold Leg Recirculation (ES1.3) j K/A
Reference:
006020A4.02 3.9/3.8, Task ID #:0060160101 l 006000A4.02 4.0/3.8 006000G13 3.9/3.4,006A4.05 3.9/3.0, I 006A4.02 4.1/3.8, 2.1.23 3.9/4.0 , ! JPM Application: Ud Requal X Initial Exam [3 Training 1 4 sk Evaluation Method LOCATION TYPE Perform [] Plant Site [] Training l Simulate Simulator [3 Annual Requal. Exam [] Classroom [] OJT l l [3 Initial Operator Exam Administered By: [3 Other: I [3 BV-T NRC [] Other: , Evaluation Results
) Performer: Name: Employee No:
! Results [] SAT Time'(minutes) UNSAT* Allotted: 15 Actual: Time Critical: El Yes X No Administrative JPM [] Faulted X
- Comments (Required for UNSAT Evaluation):
Evaluation Results Check here if same as above Observer 1: Name: Employee No: Observer 2: Name Employee No: Observer 3: Name Employee No: Observer 4: Name Employee No: Time (minutes) Results Question ID Allotted Actual SAT UNSAT* Question #1 [3 [] Employee No: Question #2 [] [3 Employee No:
- Comments (Required for UNSAT Evaluation):
Evaluator (Print): Organization: Evaluator Signature Date:
b RIL #A5.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE - EVALUATOR DIRECTION SHEET I
- [y' JPM NUMBER: 2CR-529 JPM TITLE: Transfer to Cold Leg Recirculation (ES-1.3)
TASK STAN.: Valve alignments for Cold Leg Recirculation according to Step 6 of OM-53A, Procedure ES-1.3 completed. RECOMMENDED STARTING LOCATION: CONTROL ROOM DIRECTIONS: You are to simulate (perform) the task Transfer to Cold Leg Recirculation (ES-1.3). , INIT. CONDITIONS: The plant is recovering from a loss of l- Coolant Accident. The control room operators are now into OM-53A, Procedure ES-1.3 " Transfer to Cold Leg Recirculation" and entered Step 6 of that procedure. b d INIT. CUE: Your supervisor directs you to perform Step 6 of OM-53A, Procedure ES-1.3 " Transfer to f Cold Leg Recirculation"
REFERENCES:
2OM-53A.1. ES-1.3 (Iss 1B), Issue 1B, Revision 5 l} TOOLS: Shorting Bars HANDOUT: 2OM-53A.1. ES-1.3 l a i
RTL #A5.635.J O
!& NUMBER TITLE
'2CR-529 Transfer to Cold Leg Recirculation ,
1 j l STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.) - INSTRUCTOR NOTE: Init IC-13 l
. Malf RCS 3C, 0, 0, D l Depress Reheater Reset P.B.
Stop all 3 RCPs. Open 2CCS*AOV118, Verify an j Air compressor RUNNING. l Isolate CNMT vents and drains. 2CVS*P21A/B PTL 2DAS*P204A/B Stop (A.j [). 2DGS*P21A/B Pull to Lock Reset SI both trains L Stop both EDG's. Wait until RWST level <440" reset CIA & CIB. - 1 Ensure 2CHS*P21A/B running. Place both LHSI pumps in PTL. Energize charging pump suction and discharge ; valves via LOA LOV 93 thru 96, O, D and LOV 102 thru 105, O, D Insert following to trip [2RSS*P21D) CLF PMP CSS 10 2, O, D (write snap] Start Time: I
- 1. Obtain a copy of 1. Candidate locates ES-procedure ES-1.3 of 1.3 of 20M-53A 20M-53A.
l COMMENTS P O Page 1 of 5 - w + -r y
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l i RTL #A5.635.J ' ' i I'k NUMBER TITLE 2CR-529 Transfer to Cold Leg Recirculation l 1 STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.) ,
- 2. Verify TWO charging / 2 '. Candidate locates HHSI pumps running. control and indications for HHSI pumps and verifies two pumps running.
EVALUATOR CUE: Charging pumps 21A and 21B are running. O l( D l COMMENTS l l 3.C Insert shorting bar 3.C Candidate locates jack ' l into (2 SIS *MOV836) High for 2 SIS *MOV836 and l Head SI Cold Leg Isol. inserts shorting bar. Valve Jack. COMMENTS l 4.C Open 2 SIS *MOV636 HHSI 4.1 Candidate locates j Cold Leg Isol. Valve. control switch for l 2 SIS *MOV836. I 4.2.C Candidate ~ opens 2 SIS *MOV836 4.3 Candidate verifies ! open (red) light is energized. COMMENTS
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RTL #AS.635.J . 1 J ( NUMBER TITLE l 1 2CR-529 Transfer to Cold Leg Recirculation I STEP STANDARD (Indicate "S" for Sat. or "U" ; ("C" denotes critical step) for Unsat.) 1
- 5. Verify Recirc Spray pumps 5.3 Candidate locates ;
21C and 21D - Both control and l running. . indications for Recirc Spray Pumps. 5.1 Candidate verifies 21C running. l 5.2. Candidate verifies 21D NOT running. EVALUATOR CUE: , Pump will l 'u not start. Maintenance investigating. Electrical I ! COMMENTS l l e 4 V Page 3 of 5
RTL #A5.635.J
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., ( '- D) NUMBER TITLE 2CR-529 Transfer-to Cold Leg Recirculation STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step)' for Unsat.) 6.C Insert shorting bar '6.1.C Candidate locates into appropriate jacks jacks for and then close 2CHS*MOV8132A & B and appropriate HHSI pump inserts shorting bars. discharge isolation valves. 6.2 Candidate locates control switches for 2CHS*MOV8132A & B 2CHS*MOV8132A&B OR > 6.3.C Candidate closes 2CHS*MOV8133A & B 2CHS*MOV8132A & B 6.4 Candidate verifies. closed green lights . energized OR 6.5 Candidate locates jacks for 2CHS*MOV8133A & B and inserts shorting bars. 6.6 Candidate locates control switches for 2CHS*MOV8133A&B 6.7.C Candidate closes 2CHS*MOV8133A&B 6.8 Candidate verifies closed (green) lights energized. COMMENTS Page 4 of 5
RTL #A5.635.J O NUMBER TITLE 2CR-529 Transfer to Cold Leg Recirculation 9 STEP STANDARD (Indicate "S" for Sat. or "U" , ("C" denotes critical step) for Unsat.) ! i I 7.~ Verify 2 SIS *F1945, 7. Candidate locates (946) LHSI Train A & B 2 SIS *F945, 946 and flow is indicated. . verifies flow. COMMENTS .
- 8. Verify (2 SIS *FI940, 8. Candidate locates 943] Train A, B flow - 2 SIS *FI940, 943 and indicated. verifies flow.
- 9. Go to step 7 9. Candidate commences r
O to go to Step-7. EVALUATOR CUE: The procedure step actions for - this JPM are complete. l 1 i l i l Stop Time:
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(~ RTL #A5.635.J BVPS JOB PERFORMANCE MEASURE a ORAL QUESTION #1
- l. -
l While operating in Mode 3 with the RCS pressurized to 1100 l psig, you receive annuciator Al-4A " ACCUMULATOR LEVEL / PRESSURE } HIGH/ LOW" The "A" accumulator level is observed to be 65.5% on both level transmitters (2 SIS *LI920 and 921). No filling, 7 draining, or sampling of the accumulator is in progress. What actions are required. Include any time limits and the basis for the time limits. l 9 r l ANSWER: Within 1 hour restore accumulator level to I within TS limits [by draining the accumulator). Or be in HOT SHUTDOWN within next 6 hours. The 1 hour with an inoperable accumulator minimizes the time exposure of the plant to-a LOCA event occurring concurrent with failure of another. , accumulator which may result in unacceptable peak clad temperatures l TIME 3 minutes ALLOTTED: D KSA #: 2.1.12 4.0 , l l REF: 20M-11.4.AAC issue 1 rev. 20 Tank Curve Book rev. 2 , TS 3.5.1 and basis amend. 86 COMMENTS: i
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RTL #A5.635.J BVPS JOB PERFORMANCE MEASURE l r I e ORAL QUESTION #2 f \- 14.5 hours after a Loss of Coolant Accident the Recirc Spray i . Pumps 2RSS*P21C,D and High Head SI pumps 2CHS*P21A,B are running. Using the VONDs describe the "A" train flow path for
- i accomplishing a transfer to Hot Leg Recirculation l l L l
' ANSWER: To align Recirculation Spray Pumps for Hot Leg Recirculation.
- 1. VERIFY 2RSS*P21C running l
- 2. CLOSE 2 SIS *MOV8888A
- 3. OPEN 2 SIS *MOV8887A
- 4. OPEN 2 SIS *MOV8889 To align HHSI pump for Hot Leg Recirculation i
- 1. CLOSE 2 SIS *MOV836 j'
- 2. OPEN 2 SIS *MOV869A l TIME 4 minutes
-ALLOTTED:
KSA #: 006 kl.03 (4.2/4.3) s L) REF: OM 2.53A.1.ES-1.4 Issue 1B, Rev.3 COMMENTS: i l l !O >> 6
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t RTL.#AS.635.J !O I
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- THIS SHEET TO BE GIVEN TO CANDIDATE * *
\ l BVPS JOB PERFORMANCE MEASURE ORAL QUESTION #2 14.5 hours after a Loss of Coolant Accident the Recirc Spray Pumps 2RSS*P21C,D and High Head SI pumps 2CHS*P21A,B are running. Using the VONDs describe the "A" train flow path for l l accomplishing a transfer to Hot Leg Recirculation . l l i l ~ 1 t \O
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RTL #AS.635.J
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- THIS SHEET TO BE GIVEN TO CANDIDATE *
- BVPS JOB PERFORMANCE MEASURE ORAL QUESTION #1 While operating in Mode 3 with the RCS pressurized to 1100 psig, you receive annuciator Al-4A " ACCUMULATOR LEVEL / PRESSURE HIGH/ LOW" The "A" accumulator level is observed to be 65.5% on both level transmitters [2 SIS *LI920 and 921). No filling, draining, or sampling of the accumulator is in progress. What actions are required. Include any time limits and the basis for the time limits.
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9 L L \r O I l
, RTL #AS.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE
( l i CANDIDATE DIRECTION S!!EET l l
- THIS SHEET TO DF GIVEN TO CANDIDATE
- Read:
Task': lTransfertoColdLegRecirculation(ES-1.3)
. satv& v L -
a11:ar rtum2 mm I INITIAL CONDITIONS: The plant is recovering from a Loss of Coolant Accident. The control room operators are now into OM-53A, Procedure ! ES-1.3 "Transfor to Cold Leg Recirculation" and entered ritep 6 of that
- . procedure. < ., m _ _
l l
.( INIT. CUE: Your supervisor directs you to perform Step-6 of L
l OM-53A, Procedure ES-1.3 " Transfer to Cold Leg Recirculation" l l _At this time, ask the evaluator any quections you have on this
~
q l JPM.* , When satisfied that you-understand the assigned task, announce "I am now beginning the JPM". Simulate performance or perform as directed the required task. Point to any indicator or component you verify or check and l announce your observations.
- Af ter determining the Task has been raet, announce "I have completed the JPM". Then hand back thin sheet to the evaluator.
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RTL #A5.640U BEAVER VALLEY JOB PERFORMANCE MEASURE EVALUATOR COVER SHEET JPM Number: 2CR-094 Rev: Sa System #: 005 ( JPM
Title:
Response to a Loss of the RHS l K/A
Reference:
000025EA1.09 3.2/3.1 Rev.0 Task ID #:0000180401 025AA1.09 3.2/3.1 Rev. 1 - JPM Application: X Requal x Initial Exam OTraining Evaluation Method LOCATION TYPE j O Training Perform O Plant Site Simulate O Simulator O Annual Requal. Exam I O Classroom O OJT l O Initial Operator Exam Administered By: O Other: BV-T O NRC i Other: 1 Evaluation Results Performer: Name: Employee No: ( Results O SAT Time (minutes) O UNSAT* Allotted: 20 Actual:
'ime Critical: Yes E No (
i ! Administrative JPM Faulted 1
- Comments (Required for UNSAT Evaluation):
( i . l Evaluation Results Check here if same as above Observer 1: Name: Employee No: Observer 2: Name Employee No: ! Observer 3: Name Employee No: l Observer 4: Name Employee No: j Time (minutes) Results 1 Question ID Allotted Actual SAT UNSAT* 1 i Question #1 Employee No: 1 1 Question #2 l Employee No:
- Comments (Required for UNSAT Evaluation):
)
i $ Evaluator (Print): Organization: j Evaluator Signature Date: l
t RIL #AS.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE i () EVALUATOR DIRECTION SHEET JPM NUMBER: 2CR-094 JPM TITLE: Response to a Loss of RHS. A STAN.: The Residual Heat Removal System is ' restored to service by performing steps 14 and 15 of AOP 2.10.1 as required. RECOMMENDED STARTING LOCATION: CONTROL ROOM - DIRECTIONS: You are to simulate (perform) the. task Response to a Loss of the RHS. INIT. CONDITIONS: The plant is in Mode 5. 2RHS*P21B has tripped due to a seized motor be'aring. 2RHS*P21A has been previously set for standby operation, and currently is NOT '( running. The NSS has decided to perform. the actions of procedure AOP 2.10.1, '
" Residual Heat Removal System Loss". AOP
-( 2.10.1 has been completed through step 13. I *~ I' The NSS directs you to perform steps 14 and - 15 of AOP 2.10.1 to start 2RHS*P21A and i restore the RHS to service. j i l
REFERENCES:
AOP 2.10.1, Issue 1A, Rev. 4 TOOLS: None HANDOUT: 2 AOP 2.10.1 and Attachments i
.O V
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RTL #AS.635.J t NUMBER TITLE
' N_/
2CR-094 Response to a Loss of the RHS 1 l l l STEP STANDARD (Indicate "S" for Sat. or "U" l ("C" denotes critical step) for Unsat.)
- Start time
EVALUATOR NOTE': . Simulator setup Init IC-1. Run. clear component level i failures RHR8 and RHR9. Use LOAs to energize 2RHS*MOV701A (LOV110) and 2RHS*MOV702B (LOC 115). Turn on recorders g-' ) . 2RHS*TR604A and B. f( Place / remove Caution tags as needed. To seize
'2RHS*P21B: (CLF PMP RHR2, ,
3, 0, D]. Ensure 2RHS*MOV750B and 750A are open. Close 2RHS*MOV 720A close 2RHS*HCV 758A. t [ EVALUATOR NOTE: Candidate may only check "A" train valves since the 21B pump is unavailable. This applies throughout this JPM. l l 4 1 l l Page 1 of 10 Revision 5a
l RTL #AS.635.J ^ () NUMBER-2CR-094 TITLE Response to a Loss of the RHS 4 l
' STEP STANDARD (Indicate "S" for Sat. or "U"
("C" denotes critical step) for Unsat.) , 1.C Check RHS System valves 1. Candidate locates open. 2RHS*MOV701A(B).
- 2RHS*MOV701A(B)
- 2RHS*MOV702A(B)
- 2RHS*MOV720A(B) i t
1.2 Verifies open (red) indicating lights are lit. 1.3 Candidate locates
)s,/"') 2RHS*MOV702A(B).
[ 1.4 -Verifies open (red) L indicating lights are - lit. 1.5 Candidate locates 2RHS*MOV720A(B). 1.6.C Place CS for 2RHS*MOV720A(B) to OPEN and verify red light lit.. l' COMMENTS: I EVALUATOR CUE: Red i indicating lights are lit. i EVALUATOR NOTE: Train 'B' valves in parentheses. Page.2 of 10 Revision Sa
RTL #AS.635.J l s
) NUMBER TITLE
- (
2CR-094 Response to a Loss of the RHS l STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.) ,
- 2. Verify CCP cooling to 2.1 Candidate locates RHR System available. 2CCP*MOV 150-1, 2
- 2CCP*MOV150-1, 2 (151-1, 2).
(151-1, 2) open.
- 2CCP*MOV 112A(B) open 2.2 Verifies open (red)
- 2CCP*MOV156-1, 2 indicating lights are (157-1, 2).open lit.
- 2CCP-FI 117A1, A2, (117B1, B2) flow 2.3 Candidate locates indicated 2CCP*MOV 112A (B).
()
'(,/
2.4 Verifies open (red) indicating lights are lit. 2.5 Candidate locates - 2CCP*MOV 156-1, 2 (157-1,2). 2.6 Verifies open (red) indicating. lights are lit. 2.7 Candidate locates flow indicator 2CCP-FI11'/A1 (A2, 117B1, B2). 1 2.8 Verifies flow indicated. I COMMENTS: 1 i l q ,7 I Page 3 of 10 Revision 5a
i, RTL #AS.635.J sxe NUMBER TITLE l(g \_s)- 2CR-094 Response to a Loss of the RHS l I 1 STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.) 1 l' EVALUATOR CUE: All valves have red indicating lights lit. CCP flow is 6000 gpm. L 3. Close RHR discharge 3.1 Candidate locates L flow path throttle 2RHS*HCV758A (B) l valves. controller (s).
- 2RHS*!!CV758A (B) 3.2 Verifies / closes I((N )
L - 2RHS*FCV605A (B) valves, demand at 100%. l 3.3 Candidate locates
)
2RHS*FCV605A (B) l controller (s). 3.4 Verifies / closes
. valves, demand at 0%.
l COMMENTS: l 4.- Check if RHR pump 21A 4 .1- Candidate requests has been vented. pump venting status. COMMENTS: t l l i ( ' b') L EVALUATOR CUE: Pump has l 1.d s been recently vented. l-Page 4 of 10 Revision Sa
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tRTL.#A5.635.J NUMBER TITLE [(_ ) 2CR-094 Response to a Loss of the RHS l STEP STANDARD ; (Indicate "S" for Sat. or "U" l ("C" denotes critical step) for Unsat.) EVALUATOR CUE: 2RHS*P21B : has tripped due to a seized I motor bearing and is . unavailable. ) 5.C Start one RHR pump. 5.1 Locates control switch I for 2RHS*P21A. q l 5.2.C Turns control switch to start. fs I {\-) 5.3 Verifies red light energizes. EVALUATORS NOTE: Candidate
]
may also use pump amps and/or recirc flow as indications for pump start. I EVALUATOR CUE: Pump indicating light is red. I COMMENTS
- l l-Page 5 of 10 Revision 5a
RTL #AS.635.J p NUMBER TITLE 2CR-094 Response to a Loss of the RHS STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.)
- 6. Maintain RCS level. 6. Candidate checks level is stable on 2RCS*LI462.
EVALUATOR NOTE: Candidate may use 2RCS*LI459, 460, 461 and/or computer points to check RCS level trends. O) ( EVALUATOR CUE: 48 percent on cold cal RCS level is ( level indicator 2RCS*LI462 and stable. . COMMENTS: EVALUATOR CUE: It is desired to have approximately 3000 gpm RHS flow, including recirculation flow.
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l RTL #AS.635.J
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( NUMBER TITLE 2CR-094 Response to a Loss of the RHS l STEP STANDARD (Indicate "S" for Sat. or "U" I ("C" denotes critical step) for Unsat.) 7.C Gradually raise-RHR 7.1 Candidate locates l bypass flow rate until 2RHS*FCV605A i l' flow is restored. controller. ! 7.2.C Opens valve until flow increases. i l 7.3 Verifies flow approximately 3000 l gpm. l(h /'v/ EVALUATOR CUE: RHS flow is 3000 gpm. 1 l 1 COMMENTS: I l l f . 4 i f% l 4 l Page 7 of 10 Revision 5a
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RTL #AS.635.J.
) NUMBER TITLE 2CR-094 Response to a Loss of the RHS l
i STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.) l l L 8.C Establish RCS cooldown 8.1 Candidate locates rate less than 50 F/Hr. 2RHS*HCV758A. 8.2.C Opens valve to begin l cooldown. 8.3 Checks cooldown rate less than 50 F/Hr.
.:p) (, EVALUATOR NOTE: Due to time considerations, once flow is established through the l
Heat exchanger. - Give the , cue following Step 8. l , EVALUATOR CUE: Cooldown rate is 35 F/Hr. I- COMMENTS i: y Page 8 of 10 Revision Sa
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li . RTL #AS.635.J [% /') NUMBER TITLE 2CR-094 Response to a Loss of the RHS STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.)
- 9. Verify following 9.1 Candidate. locates the Parameters: following and verifies Pump Amps - Steady each parameter.
Pump flow - Greater - Pump Amps 2RHS-1 than 1500 GPM 121A CCP Temperature - - Pump Flow 2RHS-FI NORMAL 605A CCP Pumps - At Least - CCP Temperature One Running 2CCP-TI 110A CCP Valves - Aligned to - CCP Pumps - One l RHR Loop Running
- CCP Valves Aligned l (<- )
j to RHR Loop 2CCP*MOV112A i EVALUATOR CUE: Give the , following as candidate l checks parameters: l , Pump Amps = 29 [ Pump Flow = 3000 gpm plus recirc CCP Temperature = 90 F CCP Pumps = two running CCP Valve 2CC*MOV112A Open If candidate verifies other i CCP valves cue as given in j previous steps. l' COMMENTS: 4
,4 f
o Page 9 of 10 Revision Sa
RTL #A5.635.J
.( NUMBER TITLE 2CR-094 Response to a Loss of the RHS STEP STANDARD (Indicate "S" for Sat. or "U"
("C" denotes critical step) for Unsat.) STOP TIME: ( O C 'l Pag 10 of 10 Revision 5a
. 1 l
RTL #AS.635.J BVPS JOB PERFORMANCE MEASURE [' ORAL QUESTION #1 The Low Temperature Overpressure Protection System (OPPS) is in service in Mode 4. The three RCS Hot Leg temperatures as indicated on 2RCS-TI413, 423, & 433 are 196 F, 19 5 F , 197 F. Based upon this data determine the minimum RSC operating pressure which will actuate OPPS? ANSWER: Select the lowest T H 195 F and read the corresponding RCS pressure of 520 psig. ' [ GRADER DISCRETION REQUIRED) , TIME 5 minutes ALLOTTED: KSA #: 005000A1.01 3.5/3.6 Rev.0 005A2.02 3.5/3.7 Rev. 1 REF: 20M51.4.C.IV.B Issue 4 Rev. 11
" Plant Cooldown to Mode 4" step 8
/\
' Unit 2 Curve Book CB-25 Issue 7 Rev.0 i '%-
\
"RCS Cold Over pressurization Protection System Setpoint Program".
COMMENTS: - e 1
- d 9
^
RTL #AS.635.J- BVPS JOB PERFORMANCE MEASURE A- ORAL QUESTION #2
\,
The plant is shutdown preparing to place RHR into service. The RHR system Motor Operated Valves are energized with the suction and discharge valves still closed. What is the effect upon the RHR system should the 21A RHR Pump Test push button be depressed? ANSWER: .The "A" RHR pump will start and run. TIME 5 minutes ALLOTTED: KSA #: 005A4.01 3.6/3.4 REF: 20m10.1.D. Issue 4 Rev.0 "RHR Pumps" COMMENTS: 4 b ./ .; i
RTL #A5.635.J (- *
- THIS SHEET TO BE GIVEN TO CANDIDATE * ,
BVPS JOB PERFORMANCE MEASURE ORAL QUESTION #2 The plant is shutdown preparing to place RHR into service. The RHR system Motor Operated Valves are energized with the suction and discharge valves still closed. What is the effect upon the RHR system should the 21A RHR Pump Test push button be . depressed? O O e O '
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RTL #AS.635.J G U *
- THIS SHEET TO BE GIVEN TO CANDIDATE *
- BVPS JOB PERFORMANCE MEASURE ORAL QUESTION #1 .
The Low Temperature overpressure Protection System (OPPS) is in service in Mode 4. The three RCS Hot Leg temperatures as indicated on 2RCS-TI413, 423, & 4 3 3 are 19 6"F, 19 5 F , 197 F . Based upon this data determine the minimum RSC operating pressure which will actuate OPPS? l 1 l' t (. l l . 1 L i 4 1 (-
RTL #AS.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE I
,_ CANDIDATE DIRECTION SHEET
)
./
- l THIS SHEET TO BE GIVEN TO CANDIDATE * '
l l Read: l l l Task l Response to a Loss of the RHS. l l l INITIAL CONDITIONS: lTheplantisinMode5. ' 2RHS*P21B has tripped due to a seized motor bearing. 2RHS*P21A has been previously set for j standby operation, and currently is NOT running. The NSS has decided to perform the actions of procedure AOP 2.10.1,
" Residual Heat Removal System Loss". AOP 2.10.1 has been completed through step 13.
INIT. CUE: The NSS directs you to perform steps 14 and 15 of
#')/ AOP 2.10.1 to start 2RHS*P21A and restore the RHS to service.
At this time, ask the evaluator any questions you have on this JPM. When satisfied that you understand the assigned task, announce "I am now beginning the JPM". Simulate performance or perform as directed the required task. Point to any indicator or component you verify or check and announce your observations. After determining the Task has been met, announce "I have completed the JPM". Then hand back this sheet to the evaluator. l
.s /
i . . 1 . I
- RTL #A5.640U BEAVER VALLEY JOB PERFORMANCE MEASURE
- EVALUATOR COVER SHEET '
i i JPM Number: 2CR-097 Rev: Sa System #: 064 Faulted: O F JPM
Title:
Transfer Bus 2AE from Emergency to Normal Feed / Bus 2A
- K/A
Reference:
064 A4.07 3.4/3.4, Rev. 1 Task ID #:0640060101 064000 A4.07 3.4/3.4 Rev.0 ; j JPM Aylication: Requal O Initial Exam O Training i Evaluation Method LOCATION TYPE l Perform Plant Site O Training { Simulate Simulator Annual Requal. Exam Classroom OJT j Initial Operator Exam f Administered By: Other: i i O Bv-T ! NRC i ! Other: f Evaluation Results ! Performer: Name: Employee No: l . Results O SAT Time (minutes) l ) UNSAT* Allotted: 20 Actual: Time Critical: Yes X No l ,
~
l
- Comments (Required for UNSAT Evaluation):
l Evaluation Results Check here if same as above Observer 1: Name: Employee No: Observer 2: Name Employee No: Observer 3: Name Employee No: _ Observer 4: Name Employee No: Time (minutes) Results , Question ID Allotted Actual SAT UNSAT* Question #1 Employee No: , Question #2 l Employee No:
- Comments (Required for UNSAT Evaluation):
l l l Evaluator (Print): Organization: l l Evaluator Signature Date: l l
i RIL #AS.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE g"} EVALUATOR DIRECTION SHEET
!\ J
.JPM NUMBER: 2CR-097 JPM TITLE: Transfer Bus 2AE from Emergency to Normal Feed / Bus 2A TASK STAN.: Bus 2AE is energized from Bus 2A. The #1 EDG is shutdown.
RECOMMENDED j STARTING LOCATION: CONTROL ROOM i DIRECTIONS: You are to simulate (perform) the task Transfer Bus 2AE from Emergency to Normal Feed / Bus 2A. INIT. CONDITIONS: The plant is in Hot Standby. Breaker 2A10 has spuriously tripped open.- All normal 4KV busses are energized from S$ST's 2A and 2B. The #1 EDG is running and carrying loads on the AE Bus. The 4KV normal to ; l p f 'g emergency tie breakers, 2A10 and 2E7, are { y; OPen. INIT. CUE: Your supervisor tells you to transfer Bus
- 2AE to Bus 2A and to shutdown the #1 EDG in .
l accordance with the appropriate procedure.
REFERENCES:
20M-36.4.E Issue 4 Revision 4 I l TOOLS: None l l HANDOUT: 20M-36.4.E l l b p).
\~-
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1 RTL #AS.635.J h ((Y NUMBER TITLE l I 2CR-097 Transfer Bus 2AE from Emergency to Normal Feed / Bus 2A STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.) . Start time: EVALUATOR NOTE: Init. IC-5. Activate: BKR HIV1 1,0,D. Then clear: BKR HIV1 CLR wait for D/G sequencer to complete.
- 1. Obtain the procedure. 1. The candidate obtains
,_ 20M-36.4 Procedure E.
( . COMMENTS: EVALUATOR CUE: It will be necessary to, role play the second verification of steps throughout this JPM. Cue the candidate as needed. l l l i i Page 1 of 11 Revision Sa o
RTL #AS.635.J b~-I NUMBER TITLE 2CR-097 Transfer Bus 2AE from Emergency to Normal Feed / Bus 2A STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.) 2.C. Close breaker 2A10, 4KV 2.1.C The candidate Bus 2A to Emergency Bus momentarily places the 2AE breaker 2A10 control switch in the CLOSE position. 2.2 The candidate verifies the red light above breaker 2A10 control switch is ON. (D EVALUATOR NOTE: Only provide the following CUES if simulating performance of . this task. EVALUATOR CUE: The red light is ON. COMMENTS: l l 3.C. Place the 2-1 Diesel 3.C. The candidate places l Generator synchronizing EMERG GEN 1 switch in the Bus 2A SYNCHRONIZING SEL SW position. in the Bus 2A position. COMMENTS: YY ~ Page 2 of 11 Revision 5a
RTL #AS.635.J f NUMBER TITLE 2CR-097 Transfer Bus 2AE from Emergency to Normal Feed / Bus 2A a STEP STANDARD (Indicate "S" for Sat. or'"U" ("C" denotes critical step) for Unsat.) 4.C Adjust 2-1 EDG until 4.1. The candidate observes the synchroscope needle the 2-1 Emergency-is rotating-SLOW in the Diesel Generator FAST DIRECTION. -synchroscope on the Vertical Board. EVALUATOR NOTE: IF the candidate observes the SYNCHRONIZING NORMAL OR EMERGENCY synchroscopes, eif w) THEN provide,the following cue: The needle.is not moving. The lights are off. . EVALUATOR CUE: The needle
, is rotating FAST in the SLOW DIRECTION.
4.2. The candidate adjusts the EMERG GEN 2-1 GOVERNOR control switch. O l l Page 3 of 11 Revision 5a
l 6 RTL #A5.635.J q. l\ NUMBER TITLE 2CR-097 Transfer Bus 2AE from Emergency to Normal Feed / Bus 2A STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.) , EVALUATOR CUE: IF the candidate goes'to the LOWER i position, THEN inform the I candidate the needle is rotating faster in the SLOW DIRECTION. IF the candidate goes to the RAISE position, l THEN inform the candidate the needle is rotation lAr)' SLOWLY in the SLOW DIRECTION. j 4.3.C. Candidate obtains the ' synchroscope rotating slowly in the fast direction. l - COMMENTS: j i I L ! ! I l 3 i ^ 1%
. E,!
Page 4 of 11 Revision 5a
__ _ _. - _. - . _ _ _ _ _ . . . ~ _ - - - RTL #AS.635.J. e 4 (_(_) NUMBER TITLE l 2CR-097 Transfer Bus 2AE from Emergency to Normal l Feed / Bus 2A j i^ i i STEP' STANDARD (Indicate "S" for Sat. or "U" r ("C" denotes critical step) for Unsat.)
- 5. Adjust 2-1 Diesel 5.1 The candidate locates Generator voltage to be EMERG GEN 2-1 VOLTS ,
slightly higher than . meter and compares it Bus 2A voltage by using to 4KV Bus 2A VOLTS ! voltage adjust switch, meter., l 5.2 Candidate verifies Diesel Generator ; volts slightly higher ; than bus volts and l
. adjusts Emergency l 1
Generator 2-1 Voltage Adjust if necessary. EVALUATOR CUE: Emergency GEN 2-1 volts meter indicates 123.8 volts and 4KV Bus 2A volts meter indicates 122 volts. COMMENTS: 7 Page 5 of 11 Revision Sa
RTL #A5.635.J
) NUMBER TITLE ,
1 2CR-097 Transfer Bus 2AE from Emergency to Normal Feed / Bus 2A l STEP STANDARD ' (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.) 6.C. Close breaker 2E7"when 6.1 The candidate monitors synchroscope, rotating the 2-1 Emergency SLOWLY in FAST . Diesel Generator DIRECTION. synchroscope on the Vertical Board. EVALUATOR CUE: The needle j is rotating VERY SLOWLY in l the FAST DIRECTION. The
/' needle is at 5 min. till 12
( ,N) position. 6.2.C. The candidate momentarily places the - breaker 2E7 control switch in the CLOSE position when the
. synchroscope is 4 between 5 to 12 and 12 o' clock.
6.3. The candidate verifies the red light above breaker 2E7 control switch is ON. EVALUATOR CUE: The red light is ON. COMMENTS: r~N i' l i ! Page 6 of 11 Revision 5a I'
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b RTL #A5.635.J [t's / NUMBER TITLE l j 2CR-097 Transfer Bus 2AE from Emergency to Normal Feed / Bus 2A I STEP STANDARD (Indicate "S" for Sat. or "U" ! ("C" denotes critical step) for Unsat.) l
- 7. Place the 2-1 EDG 7.1 The candidate places synchronizing Switch is EMERG GEN 2-1 OFF. . SYNCHRONIZING SEL SW
! in the OFF position. l COMMENTS:
- 8. Maintain generator 8.1. The candidate locates power factor between Emergency Generator
,fs 0.8 and 1.0 lagging, as Power Factor meter. indicated on Emergency ' .{ } Generator Power Factor, by adjusting Emergency Generator 2-1 Voltage _ Adjust. 8.2. Candidate adjusts voltage adjust as needed to maintain between 0.8 and 1.0 lagging PF. EVALUATOR CUE: Emergency Generator Power Factor is 0.95 lagging. COMMENTS: l l f i lk/ Page 7 of 11 Revision 5a 4
RTL #A5.635.J-l [~% * ( lNUMBER TITLE L 2CR-097 Transfer Bus 2AE from Emergency to Normal j Feed / Bus 2A i ! STEP STANDARD l (Indicate "S" for Sat. or "U" [ ("C" denotes critical step) for Unsat.) ! 9. Reduce load on the EDG 9.1. The candidate to <100 KW. intermittently places l the EMERG GEN 2-1 l GOVERNOR control switch in the LOWER position. 9.2 The candidate monitors l the following parameters during the t s~ load decrease: i
- a. EMERG GEN 1 VOLTS
- b. EMERG GEN 1 POWER FACTOR .
- c. EMERG GEN 1 WATTS 9.3 The candidate
! intermittently places i the EMERG GEN-1 VOLT ADJUST switch in LOWER.
- 9.4. The candidate stops reducing load when the EDG output is '
<100 KW as read on Emergency Generator 2-1 watts meter.
l- ' l' l' EVALUATOR CUE: Watts l indicate 90 KW. I e COMMENTS: lU I' I Page 8 of 11 Revision 5a
l l l RTL #A5.635.J l
. ,0 -
l( NUMBER TITLE i 2CR-097 Transfer Bus 2AE from Emergency to Normal Feed / Bus 2A r l l
)
1 1 l STEP STANDARD . (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.) l l EVALUATOR NOTE: As needed, provide the following cues: i EDG voltage is 128, power factor is 0.8. j 4 10.C. Open breaker 2E10. 10.1.C. The candidate ! ! momentarily - aces the ! breaker 2El' antrol switch in TP.P. j A g ,] t 10.2. The candidate verifies the white light above l breaker 2E10 control switch is ON. - i-l l EVALUATOR CUE:' The white
, light is ON.
l COMMENTS: I- 11. Verify 4KV Bus 2AE 11. The Candidate verifies Volts is 2 120 volts. 2AE Bus Voltage 2 120. EVALUATOR CUE: Voltage is 125 volts. COMMENTS: 1
'O '\J Page 9 of 11 Revision 5a l'
RTL #AS.635.J 1
/O ! I l kJ NUMBER TITLE 2CR-097 Transfer Bus 2AE from Emergency to Normal l Feed / Bus 2A j I
l l STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.) I
- 12. Verify EDG voltage is 12. The canclidate verifies 125 volts as read on EMERG GEN 2-1 VOLTS is Emerg Gen 2-1 volts. 125 VAC.
I ( 'N EVALUATOR CUE: Voltage is
! ) 125 VAC.
COMMENTS:
- 13. Verify annunciator 13. The candidate verifies Window No. A8-4B, Annunciator A8-4B is DIESEL GEN 2-1 M.O. not in alarm.
GROUND SWITCH NOT FULLY OPEN, is NOT alarmed. EVALUATOR CUE: The annunciator A8-4B is not Lit. COMMENTS:
- 14. Allow engine to cool 2 14. The candidate waits 2 to 3 minutes. to 3 minutes before proceeding.
COMMENTS: EVALUATOR CU_E: 3 minutes (n)
%/
have elapsed. r Page 10 of 11 Revisi sii 5a i l
RTL #AS.635.J i ( - NUMBER TITLE j 2CR-097 Transfer Bus 2AE from Emergency'to Normal Feed / Bus 2A i STEP' STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.) 15.C. Simultaneously depress 15.1.C. The candidate both engine stop SIMULTANEOUSLY buttons, depresses both EMERG GEN 1 STOP pushbuttons. 15.2. The candidate verifies EMERG GEN 2-1 RPM decreases and releases pushbuttons. p EVALUATOR CUE:. Speed is decreasing and then the
- 4) diesel generator stops.
~
COMMENTS:
- 16. , Place the 2-1 EDG Auto 16. When the EDG is Exercise switch in stopped the candidate NORMAL. verifies the EMERG GEN 2-1 AUTO EXERCISE SEL switch is in NORMAL.
COMMENTS: EVALUATOR NOTE: Inform Candidate another operator l will complete steps 9 thru ! 11. Stop Time: I v 1 Page 11 of 11 Revision 5a l
lg RTL #AS.635.J BVPS JOB PERFORMANCE MEASURE yt }
\
ORAL QUESTION #1 Which emergency diesel generator trips REMAIN FUNCTIONAL after an i emergency start of the diesel generator on bus undervoltage. i ANSWER: 1. Engine overspeed
- 2. Backup phase fault detection
- 3. Generator differential current i 4. Generator over-excitation
[ Evaluator note: If the candidate uses.20M-36.1.D to obtain answers, be aware that the l wording in the OM will be slightly different in l l that phase fault and differential trips are broken down into specific relay trips. These are not required for full credit] TIME ALLOTTED: 4 minutes I f KSA #: 055EA1.06 4.1/4.5 Rev. 1 l( REF: T.S.3.8.1.1, SR 4.8.1.1.2.b.4, Amend 79 . COMMENTS: , I l L i f )\
- \_
F. l
. ._ . . . . _ _ ._ __ -_ . . _ . . _ . . _ . . ~ ~ _ _ RTL'#AS.635.J- ;BVPS JOB PERFORMANCE MEASURE.
. - - ORAL QUESTION #2 j "'N / Describe the normal flow path for Vital Bus no. 1 beginning fromJthe 480 volt source and ending at the Vital Bus loads.
ANSWER: 1. 480 VUS*2-8 TO
- 2. MCC2-E05 TO
- 3. BAT *CHG2-1 TO
- 4. UPS*VITBS2-1 (AND BAT *2-1) TO (a. CB131 DC INPUT)
(b.: Blocking Diode) (c. Inverter) !
- 5. Vital Bus Loads i
NOTE: Items in parentheses is NOT required for .
-full credit.
TIME ALLOTTED: 4 minutes KSA #: 062 A3.05 3.5/3.6 Rev. 1 l i REF: 20M-38.1.B Page 2 of 3 Issue 4 Rev. 1 20M-38.5 Fig. 38-1 Issue 4 Rev. 3 f') N./ i COMMENTS:- ! G e [ .- l i i wh j 'y ' J - r. I' l i. i.
. . . . . . . . - . . - - _ . - . - . . - . - . . . . . . - . . . . . . _ . - . . . . . - ~ . . . - - . . - - . . . . . _ . . - . . . . . ~ . . . - . . .
1 RTL'#AS.635.J- 'I *
- THIS SHEET TO BE GIVEN TO CANDIDATE *
- BVPS JOB PERFORMANCE MEASURE ORAL QUESTION #2 Describe the normal flow path for Vital Bus no. 1 beginning from the-480 volt source.and ending at the Vital Bus loads.
O O 4 V
_ . . . - . ~ . - _ _ _ . _ . _ . . . ~ _ _ . _ . _ . . ~ . _ . _ _ _ _ . _ _ _ _ . . _ _ . _ _ l
'RTL #AS.635.J- ,
1 (' *
- THIS SHEET TO BE GIVEN TO CANDIDATE *
- 1 l
BVPS JOB PERFORMANCE MEASURE , 1 ORAL QUESTION #1 , Which emergency diesel generator trips REMAIN FUNCTIONAL after an emergency start of the diesel generator on bus undervoltage'. 1 1 l I i l l l l
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RTL'#AS.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE CANDIDATE DIRECTION SHEET j-s . D
- THIS SHEET TO BE GIVEN TO CANDIDATE
- Read:
Task: lTransferBus2AE.fromEmergencytoNormalFeed/ Bus 2A INIT'IAL CONDITIONS: The plant is in Hot Standby. Breaker 2A10 has spuriously tripped open. All normal 4KV busses are energized from SSST's 2A and 2B. The #1 EDG is running and carrying loads on the AE Bus. The 4KV normal to emergency tie breakers, 2A10 and 2E7, are open. INIT. CUE: Your supervisor tells you to transfer Bus 2AE to Bus 2A and to shutdown the #1 EDG in accordance ('] with the appropriate procedure. , g,,/ At this time, ask the evaluator any questions you have on'this JPM. When. satisfied that you understand the assigned task, announce "I am now beginning the JPM". Simulate performance or perform as directed the' required task. Point to any indicator or component you verify or check and announce your observations. After determining the Task has been met, announce "I have completed the JPM". Then hand back this sheet to the evaluator. l i C\ -Q l l
. . - . - _ - . ~ ~
i 1 !. RTL #A5.6400 BEAVER VALLEY JOB PERFORMANCE MEASURE i EVALUATOR COVER SHEET JPM Number: 2CR-622 Rev: 2a System #: 073 } JPM
Title:
Respond To Radiation Monitor Alarm (Leak Collect Vent) I ! ! K/A
Reference:
073000A4.02 3.7/3.7 Task ID #:0730030101 JPM Application: X Requal X Initial Exam [3 Training I j Evaluation Method LOCATION TYPE i [3 Perform Plant Site [3 Training Simulate Simulator Annual Requal. Exam k Classroom OJT Initial Operator Exam l Administered By: Other: i l BV-T [3 NRC [] Other: 4 j { Evaluation Results Performer: Name: Employee No: l l Results SAT Time (minutes) j [] UNSAT* Allotted: 20 Actual: ) Time Critical: Yes X No 4 Administrative JPM Faulted X l l
- Comments (Required for UNSAT Evaluation):
Evaluation Results [3 Check here if same as above Observer 1: Name: Employee No: Observer 2: Name Employee No: __ Observer 3: Name Employee.No: ) Employee No: Observer 4: Name Time (minutes) Results Question ID Allotted Actus) SAT UNSAT* i 1 Question #1 Employee No: l Question #2 Employee No:
- Comments (Required for UNSAT Evaluation):
Evaluator (Print): Organization: Date: Evaluator Signature
RIL #AS.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE EVALUATOR DIRECTION SHEET JPM NUMBER: 2CR-622 JPM TITLE: Respond To Radiation Monitor High Alarm (Leak Collect Vent) TASK STAN.: Radiation monitor automatic actions have been verified. RECOMMENDED STARTING LOCATION: CONTROL ROOM l DIRECTIONS: You'are to simulate (perform) the task Respond To Radiation Monitor High Alarm (Leak Collect. Vent). INIT. CONDITIONS: The plant is currently at 100% power. Annunciator A4-SC has just come in. Your cupervisor directs you to utilize the appropriate Alarm Response Procedure to respond to the alarm. l
- ('~h N-) INIT. CUE: Your supervisor directs you to respond to the alarm by using the appropriate alarm response procedure.
REFERENCES:
2OM-43.4 AEB Issue 1, Revision 5 20M-43.4 AAC, Issue 4, Revision 0 TOOLS: None HANDOUT: 20M-43.4 AEB and AAC I i I
RTL #AS.635.J. ( NUMBER TITLE 2CR-622_ Respond to. Radiation Monitor Alarm (Leak Collect Vent) STEP. STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.) , Start time: EVALUATOR NOTE: Simulator setup; Init. IC-13. CLF BIST, RMS218,2,3; CLF BIST, RMS219,2,D (Prevents all dampers from swap.) CLF Trans RMS90,1,1E-05,C, R2GB042.GT.O.097; CLF Trans, RMS91,1,0.1,D EVALUATOR NOTE: Steps 1 - 6 are opticnal, candidate may , not perform them. JPM is designed to begin with 20M-43.4.AEB 1.- bandidate obtains alarm 1.1. Candidate locates response procedure A4- alarm response SC, AAC Radiation procedure A4-SC. monitoring level high. COMMENTS: l i
- O r
Page 1 of 9 Revision 2a
RTL #AS.635.J e~s NUMBER TITLE 2CR-622 Respond to Radiation Monitor Alarm (Leak Collect Vent) STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.)
- 2. Verify or depress the 2.1. Candidate locates the grid six pushbutton and grid six pushbutton.
determines which rad monitor is in alarm at 2.2. Pushes the buttons or the RM-11 console. verifies that the grid is displayed. COMMENTS:
- (
- 3. At RM-11, console type 3.1. Candidate locates the in the 4 digit 4 digit code for 2RMR-numerical code for the RQI301. .
monitor in alarm and presses the select pushbutton. 3.2. Types in the code and presses the select pushbutton. EVALUATOR CUE: RED high alarm is in for 2RMR-RQI301. COMMENTS: i a
~-)
i Page 2 of 9 Revision 2a l~
I RTL #AS.635.J (' NUMBER TITLE 2CR-622 Respond to Radiation Monitor Alarm (Leak Collect Vent) STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.)
- 4. Depress the STATUS 4.1. Candidate locates the pushbutton. STATUS pushbutton.
4.2. , Candidate depresses the STATUS pushbutton. I COMMENTS: , i O (V EVALUATOR NOTE: following two steps are The optional. -
- 5. Depress the SYSTEM ACK 5.1. Candidate depresses pushbutton to silence the SYSTEM ACK the console alarm. pushbutton to silence the alarm.
EVALUATOR CUE: The alarm silences. COMMENTS: O l l Page 3 of 9 Revision 2a
RTL #AS.635.J
/-m
[ ~hUMBER TITLE 2CR-622 Respond to Radiation Monitor. Alarm (Leak Collect Vent) - STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.)
- 6. Verify if radiation 6.1. Candidate compares level is greater than reading against 1000 times background. background or notifies NSS.
EVALUATOR CUE: The NSS is aware of the alarm level. COMMENTS: e G Page 4 of 9 Revision 2a
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l l RTL #AS.635.J
\
I ('N* f (Q l NUMBER TITLE ! 2CR-622 Respond to Radiation Monitor Alarm (Leak Collect Vent) i STEP STANDARD l (Indicate "S" for Sat. or "U" l ("C" denotes critical step) for Unsat.) . 7.C. Candidate determines 7.1.C. Candidate determines that leak collection 2RMR-RQI301 is in l ventilation radiation -alarm. monitor 2RMR-RQI301 is ! in alarm and then ; i refers to local alarm I response procedure for the corrective actions. 7.2. Candidate locates procedure AEB for
'~
corrective actions. lI EVALUATOR NOTE: Candidate may verbalize monitor in alarm or may just use the - correct procedure. Either action satisfies the critical step. COMMENTS: l l I h
\_/
i I l Page 5 of 9 Revision 2a l-
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RTL #AS.635.J ,
/'~'%-
(l\ Jl NUMBER TITLE 2CR-622 Respond to Radiation Monitor Alarm (Leak . Collect Vent) l STEP STANDARD (Indicate "S" for Sat. or "U" l' ("C" denotes critical step) for Unsat.) i
- 8. At the RM-11 console, 8.1. Candidate verifies !'
verify the indicating th n t- the red box moves box turns red and moves tc :te right. to the right of CHANNEL IN HIGH ALARM. EVALUATOR CUE: The alarm box to the right of CHANNEL IN HIGH ALARM IS RED. (~ 'y.) t COMMENTS:
- 9. Depress the CHANNEL 9.1. Candidate depresses L
ITEMS button and verify the CHANNEL ITEMS ! that the actual level pushbutton.
.is higher than the high alarm setpoint.
9.2. Compares actual level to high alarm setpoint. EVALUATOR CUE: The monitor i rad level is 1.00E-05 ! picCI/ml and'high alarm j setpoint is 1.71E-07. COMMENTS: O Page 6 of 9 Revision 2a m
RTL #AS.635.J ,
.g-+g ,G NUMBER TITLE 2CR-622 Respond to Radiation Monitor Alarm (Leak Collect Vent)
STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.)
- 10. Notify the NSS and 10.1. Candidate notifies NSS obtain directions of the HIGH radiation monitor alarm and asks for direction.
EVALUATOR CUE: The NSS is aware of the alarm and has notified RADCON. He asks that you perform steps 1.e and 1.f. He will perform steps ig, h, & i.
's_
COMMENTS: P l ( T, k.) Page 7 of 9 Revision 2a
RTL #AS 635.J [ NUMBER TITLE 2CR-622 Respond to Radiation Monitor Alarm (Leak Collect Vent) STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denctes' critical step) for Unsat.)
- 11. Verify that 11.1. Candidate locates 2HVS* MOD 201A and 2HVS* MOD 201A and B and 2HVS* MOD 201B are 2HVS* MOD 202A and B on closed. BSP.
11.2. Verifies that 2HVS* MOD 201A and 201B are closed and that 2HVS* MOD 202A and B are open. 11.3. Verifies that the (s
.\% ,)
damper green or red lights are lit. I EVALUATOR CUE: Dampers ! 2HVS* MOD 201A and 201B are open, RED lights are lit. Dampers 2HVS* MOD 202A and B are shut, GREEN lights are lit. n COMMENTS: l. is l- EVALUATOR CUE: If asked for ' guidance, act as supervisor l and direct opera. tor to place the dampers in their required position. t
' \J Page 8 of 9 Revision 2a
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1 RTL #A5.635.J '
/~~T .
.( - O NUMBER TITLE 2CR-622 Respond to Radiation Monitor Alarm (Leak Collect Vent) STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.) ! 12.C. Positions dampers by 12.1. Candidate locates placing the common Train'A and B control control switch to switches on the "FILT" position for Building Service both Train A and Train Panel. B. 12.2.C. Places the control l switches to the "FILT" I position... 12.3. Verifies that the damper green and red - lights are lit. ! EVALUATOR CUE: Dampers 2HVS* MOD 201A and B GREEN L lights are lit. - l 2HVS* MOD 202A and B RED lights are lit. l COMMENTS: t l Stop Time: l l [ J-Page 9 of 9 Revision 2a
-. . = _ - - . . . . . _- _ . _ _ . - . . . - .- .
l RTL #A5.635.J BVPS JOB PERFORMANCE MEASURE ("% !(V l ORAL QUESTION #1 Unit 2 completed a power increase from 35% to 100%. Below is data for specific activity of the primary coolant prior to and following the power increase. What action (s) should be taken in response to this data? Date Time Power Specific Activity (pci/ gram) 7-4-98 0746 35% 2.35E-1 7-4-98 0956 100% 3.25E+1 ANSWER: [The specific activity of the primary coolant exceeded 1.00 pCi/ gram Dose Equivalent Iodine and did NOT exceed the limit line shown on Fig. 3.4] thus requiring the specific activity to be dettrmined once per 4 hours until it is <1.0 pCi gram lI \ TIME 5 minutes *
.s /
ALLOTTED: KSA #: 076AK3.06 3.2/3.8 ! 000076EK3.06 3.2/3.8 l l REF: T.S. 3.4.8 RCS Specific Activity COMMENTS: l l l 's
- x.J
RTL #A5.635.J BVPS' JOB PERFORMANCE MEASURE j- ORAL QUESTION #2
/ .\
When Unit 2 completed the power ramp from 35% to 100% the Specific activity of the reactor coolant was 3.25E+1 uCi/ gram Dose Equivalent Iodine which exceeded the LCO. Is power operation ' permitted-to continue? Explain. 1 ANSWER: .Yes, To accommodate possible iodine spiking phenomenon which may occur following changes in Thermal Power. TIME 4 minutes ALLOTTED: l KSA #: 2.2.25 2.5/3.7 Rev. 1 000076G04 2.1/3.7 l REF: T.S. Bases %.4.8 Specific Activity (Amend 64) 1 k_, COMMENTS: e l l l - l l l' l' ( y.
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l RTL #AS.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE 1 CANDIDATE DIRECTION SHEET l
- THIS SHEET TO BE GIVEN TO CANDIDATE *
> Read: l i l Task: Respond to Radiation Monitor High Alarm (Leak C'ollect Vent) INITIAL CONDITIONS: The plant is currently at 100% power. Annunciator A4-5C has just come in. Your supervisor directs you to utilize the l appropriate Alarm Response Procedure to respond to the alarm. INIT. CUE: Your supervisor directs you to respond to the alarm by using the appropriate alarm response procedure. t At this time, ask the evaluator any questions you have on this JPM. When satisfied that you understand the assigned task, announce .
"I am now beginning the JPM".
Simulate performance or perform as directed the required task. l Point to any indicator or component you verify or check and announce your observations. After determining the Task has been met, announce "I have completed the JPM". Then hand back this sheet to the evaluator.
l j RTL #AS.635.J l l (v J l
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- THIS SHEET TO BE GIVEN TO CANDIDATE *
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L BVPS JOB PERFORMANCE MEASURE l. ORAL QUESTION #2
- When Unit 2 completed the power ramp from 35% to'100% the l Specific activity of the reactor coolant was 3.25E+1 pCi/ gram l Dose Equivalent Iodine which exceeded the LCO. Is power operation permitted to continue? Explain. -
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RTL #A5.635.J
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- THIS SHEET TO BE GIVEN TO CANDIDATE * * .
1 1 BVPS JOB PERFORMANCE MEASURE ORAL QUESTION #1 Unit 2 completed a power increase from 35% to 100%. Below is l data for specific activity of the primary coolant prior to and following the power increase. What action (s) should be taken in response to this data? Date Time Power Specific Activity (pci/ gram) 7-4-98 0746 35% 2.35E-1 7-4-98 0956 100% 3.25E+1 , ( O e O
i RTL #AS.640U BEAVER VALLEY JOB PERFORMANCE MEASURE ! EVALUATOR COVER SHEET l JPM Number: 2CR-NGW Rev: 0 System #: 071 JPM
Title:
Discharge Gaseous Waste Storage Tanks To Unit 1 Atmospheric V { K/A
Reference:
071A2.02 3.3/3.6 Task ID #:0710060101 i JPM Application: X Requal X Initial Exam Training i J 1 Evaluation Method LOCATION TYPE l [3 Perform Plant Site Training ,f Simulate. Simulator Annual Requal. Exam i Classroom OJT i l Initial Operator Exam Administered By: Other: [3 BV-T [ NRC Other: . . Evaluation Results 1 l . Performer: Name: Employee No: 1 j Results SAT Time (minutes) l ! [] UNSAT* Allotted: 15 Actual:
\- Time Critical: Yes X No Administrative JPM [3 Faulted l
- Comments (Required for UNSAT Evaluation):
i l Evaluation Results Check here if same as above
- Observer 1: Name: Employee No:
Obnerver 2: Name Employee No:
- Observer 3
- Name Employee No:
- Observer 4
- Name Employee No:
I Time (minutes) Results I Question ID Allotted Actual SAT UNSAT* Question #1 Employee No: { Question #'2 ! Employee No: 1
- Corm.nents (Required for UNSAT Evaluation):
i i i
) Evaluator (Print): Organization:
Evaluator Signature Date: ) i F
RIL //A5.635.J BEAVER-VALLEY JOB PERFORMANCE MEASURE EVALUATOR DIRECTION SHEET JPM NUMBER: 2CRNGW (f JPM TITLE: Discharge Gaseous Waste Storage Tanks To Unit 1 Atmospheric Vent TASK STAN.: 2GWS-TK25A-G are discharging to Unit 1 Atmospheric Vent. RECOMMENDED STARTING LOCATION: CONTROL ROOM ' DIRECTIONS: You are to simulate (perform) the task Discharge Gaseous Wacte Storage Tanks To Unit 1 Atmospheric Vent INIT. CONDITIONS: ' The plant is in Mole 1. All systems are in NSA. The Gaseous Waste Storage Tanks 2GWS-TK25A thru G are at 60 psig and isolated. An RWDA-G has been obtained. No Unit 1 Gas Discharges are in progress. Procedure 1/20M-19.4A.B Unit 2 GW Storage TK Disch To Unit 1 Atmos Vent has been completed through
-fN I IT. CUE:
step 7. Your supervisor' directs you to Commence Discharging Gaseous Waste Storage Tanks 2GWS-TK25A-thru G to the Unit 1 Atmospheric Vent, by performing steps 8 -18 of Procedure 1/20M-19.4A.B Unit,2 GW Stortge TK Disch To Unit 1 Atmos Vent and inform him/her when the discharge has commenced.
REFERENCES:
1/20M-19.4A.B Issue 3 Revision 6 (OMCN 1/2-97-65) TOOLS: Filled out RWDA-G HANDOUT: 20M-19.4A.B i
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RTL #AS.635.J l l 1
-s NUMBER, TITLE N/ 2CRNGW Discharge GW Storage Tanks To Unit 1 Atmospherics vent j I
STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.) Start time: 1 INSTRUCTOR SETUP: Init IC-45 This IC set used'the PLP i function to set all 7 decay i tank pressures at 60 psig. l Then check to insure all suction and discharge SOVs on the tanks are closed. CAUTION: Inlet SOVs must be closed to prevent backflow 1 to GW surge tank.
,V EVALUATOR NOTE: There are a number of steps to be performed by the Unit 1 CR staff for this procedure.
For each of these steps, CUE the candidate that the Unit 1 CR staff has performed that step, i Candidate locates procedure 1/20M-
- 19.4A.B !
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RTL #A5.635.J l NUMBER- TITLE 2CRNGW Discharge GW Storage Tanks To Unit 1 . Atmospherics Vent l STEP STANDARD (Indicate "S" for Sat. or "U" ! ("C" denotes critical step) for Unsat.) 1.C OPEN outlet valves for 1.C Candidate dispatches ' 2GWS-TK25A-G [2GWS- an operator to OPEN SOV125A2-G2] at [PNL- outlet valves.for 2GWSTP] 2GWS-TK25A-G [2GWS-SOV125A2-G2] at (PNL-i 2GWSTP] - l EVALUATOR CUE: Inform
. candidate that outlet valves for 2GWS-TK25A-G l
[2GWS-SOV125A2-G2] are OPEN COMMENTS: , 2.C Place Gaseous Waste 2.C Candidate places Storage Tank Outlet Gaseous Waste Storage Header v1v [2GWS- Tank Outlet Header vlv AOV105]to OPEN (2GWS-AOV105]to OPEN (BB-A) COMMENTS: i Page 2 of 4 Revision 0
_ . . _. . - - . .. -- -_ . . - - . - . . . - - . . = . - - . . RTL #A5.635.J i ,) NUMBER TITLE l ' 2CRNGW Discharge GW Storage Tanks To Unit 1 Atmospherics Vent STEP STANDARD (Indicate "S" for Sat. or "U" l ! ("C" denotes critical step) for Unsat.) ! 3.C Request the NSS/ANSS to 3.C Candidate requests the review the steps and NSS/ANSS to review the alignments conducted to steps and alignments this point and conducted to this authorize the point and authorize Initiation of the the Initiation of the discharge, discharge l EVALUATOR CUE: Inform the
~ candidate that as the NSS you have performed this review.
L O' COMMENTS: INSTRUCTOR NOTE: When discharge permit is released for Unit 1 to start' discharge ,Open the discharge SOVs. Tank pressure should then begin to drop. EVALUATOR NOTE: Instructions 13-17) are all Unit 1 Steps. The discharge will now be in progress as it has been initiated by the Unit 1 CR staff. D. 4
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Page 3 of 4 Revision 0
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RTL #A5.635.J g NUMBER TITLE 2CRNGW , Discharge GW Storage Tanks To Unit 1 l Atmospheries Vent 1 l STEP' STANDARD (Indicate "S" for Sat. or "U" l ("C" denotes critical step) for Unsat.) I t EVALUATOR CUE: Inform the candidate that as the Unit 1 RO the discharge has i commenced. i
- 4. Verify (2GWS-PR125] 4.1 Candidate veri'fies l Gaseous waste storage (2GWS-PR125] Gaseous I tank pressure is waste storage tank dropping for 2GWS- pressure is dropping
- TK25A. for-2GWS-TK25A.
r\ - l V 4.2 Candidate should then inform supervisor that discharge has commenced (as per JPM instructions) COMMENTS: Stop Time: , l i f O) Page 4 of 4 Revision 0
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l l l I RTL #A5.635.J BVPS JOB PERFORMANCE MEASURE l [(,,h
/ ORAL QUESTION #1 -
After discharging these tanks for 2 hours, the pressure in the l tanks is observed to be 56.56 psig. Decay tank bleed flow rate ' r recorder [FR-1GW-105) is OOS, Calculate the tanks discharge l- bleed flowrate. I ANSWER: From 1/2OM-19.4A.B step 19a Bleed Flow = (132)(60-56.56)(7) ( = 1.8 SCFM 5 minutes
' TIME ALLOTTED:
l l ' l KSA'#: 071 A4.07 3.0 , l. I p
- REF
- 1/20M-19.4A.B Issue 3 Revision 6 (OMCN 1/2-97-65)
COMMENTS: Corrected version for 7 tanks instead of 1 ' i l l i i t 9 4 v
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.RTL #AS.635.J BVPS JOB PERFORMANCE MEASURE ORAL QUESTION #2 l
t During Gaseous Waste Storage tank discharging, it is preferred that the Stability Class be A, C, or D. ( B, l What does Stability Class refer to?, and why the preference? l l-ANSWER: Stability Class is a method of classifying atmospheric conditions. Stability Class A, B, C, j or D is preferred for discharging because these classifications present the best conditions for dispersion (dilution) of the discharge.[using temperature and wind speed at various atmospheric heights l TIME 4 minutes ALLOTTED: l - KSA #: 071 A2.08 2.8 l - REF: UFSAR Section 2.3 ,[\ )] COMMENTS: l
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L' . RTL #AS.635.J
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- THIS SHEET TO BE GIVEN TO CANDIDATE * *
( BVPS JOB PERFORMANCE MEASURE ORAL QUESTION #2
- During' Gaseous Waste Storage tank discharging, it is preferred that the Stability Class be A, B, C, or D.
What does stability Class refer to?, and why the preference? l
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RTL #AS.635.J O *
- THIS SHEET TO BE GIVEN TO CANDIDATE *
- BVPS JOB PERFORMANCE MEASURE ORAL QUESTION #1 After discharging these-tanks for 2 hours, the pressure in the (
tanks is observed to be 56.56 psig. Decay tank bleed flow rate- ! recorder,'?R-1GW-105] is OOS. Calculate the tanks discharge bleed flowrate. I 1 l i i i '. I 1
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I RTL #AS.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE l CANDIDATE DIRECTION SHEET (~~j
- THIS SHEEP TO BE GIVEN TO CANDIDATE
- l x_ / ;
Read: . l 1 ask: Discharge Gaseous Waste Storage Tanks To Unit 1 Atmospheric Vent l INITIAL CONDITIONS: The plant is in Mode 1. All systems are I in NSA. The Gaseous Waste Storage Tanks l 2GWS-TK25A thru G are at 60 psig and I isolated. An RWDA-G has been obtained. No Unit 1 Gas Discharges are in progress. Procedure 1/20M-19.4A.B Unit 2 GW Storage TK Disch To Unit 1 Atmos Vent
, has been completed through step 7.
[~g ) INIT. CUE: Your supervisor directs you to Commence l Discharging Gaseous Waste Storage Tanks 2GWS-
/'
TK25A-thru G to the Unit 1 Atmospheric Vent, by performing steps 8 -18 of Procedure 1/2OM-19.4A.B Unit 2 GW Storage TK Disch To Unit 1 Atmos Vent and inform him/her when the discharge has commenced. At this time, ask the evaluator any questions you have on this JPM. When satisfied that you understand the assigned task, announce "I am now beginning the JPM". Simulate performance or perform as directed the required task. Point to any indicator or component you verify or check and announce your observations. After determining the Task has been met, announce "I have completed the JPM". Then hand back this sheet to the evaluator.
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j ' l l i l RTL #AS.6400 BEAVER VALLEY JOB PERFORMANCE MEASURE { EVALUATOR COVER SHEET l JPM Number: 2PL-NAFW Rev: O System #: 061 l JPM
Title:
Isolate AFW During Alternate Safe S/D- , l l l</A
Reference:
061A2.05 3.1/3.4 Task ID #:0610040104 j JPM Application: X Requal X Initial Exam Training l Evaluation Method LOCATION TYPE l Perform Plant Site Training l Simulate Simulator Annual Requal. Exam l
)
f Classroom O OJT : l Initial' Operator Exam Administered By: Other: I O Bv-T l l j NRC Other: l i
- Evaluation Results Performer: Name: Employee No:
j Results SAT Time (minutes) f UNSAT* Allotted: 15 Actual: Time Critical: Yes X No i Administrative JPM Faulted
- Comments (Required for UNSAT Evaluation):
i i i - . j Evaluation Results Check here if same as above ! Observer 1: Name: Employee No: Observer 2: Name Employee No: l Observer 3: Name Employee No: l ! Observer 4: Name Employee No: ! Time (minutes) Results l Question ID Allotted Actual SAT UNSAT* Question #1 Employee No: Question #2 Employee No:
- Comments (Required for UNSAT Evaluation):
O Evaluator (Print): Organization: Evaluator Signature Date:
l .. i -t ' RIL #AS.635.J BEAVER VALLEY JOB PERFORMANCE-MEASURE
.O EVALUATOR DIRECTION SHEET
., U .
(: JPM NUMBER: 2PL-NAFW
~JPM TITLE: Isolate AFW During Alternate Safe S/D j'
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- AFW flow is isolated to the "C" S/G.
RECOMMENDED
- STARTING LOCATION
- CONTROL ROOM i.
i l , . DIRECTIONS: You are to simulate (perform) the task Isolate AFW flow to "C" S/G. l l INIT. CONDITIONS: A deep. seated fire has occurred in the cable spreading area just below the Control
. Room. The NSS he; evacuated the CR and ,
activated the Alternate Shutdown Panel
. (ASP). Nuclear Operator #1 Procedure 20M-56C.4.D has been completed through step 10. I p.~ "C" S/G AFW throttle valves (2FWE*HCV100A & l BJ have been de-energized. 1 INIT. CUE:
Your supervisor directs you to perform step -
-l 11'of Nuclear Operator #1 Procedure 20M-l 56C.4.D, and-report back when you have completed this step.
o
REFERENCES:
20M-56C.4.D issue 1 rev. 8 Local Placard , l TOOLS: Simulated allen key and pump handle ! 1 { ! , HANDOUT: 20M-56C.4.D issue 1 rev. 8 l l O
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[ f. RTL #A5.635.J ( NUMBER TITLE 2PL-NAFW Isolate AFW During Alternate Safe S/D l l STEP STANDARD - , ! (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.) Sta'rt time: Candidate locates Nuclear. Operator #1 l Procedure 20M-56C.4.D l I
- 1. Refer to local placard. 1. Candidate locates i local placard in South safeguards 741'.
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COMMENTS: Y 4 EVALUATOR NOTE: The valves can be closed in any order.
- 2. Remove valve cover for 2. Candidate removes 2FWE*HCV100A. cover from (2FWE*HCV100A).
COMMENTS:
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RTL #AS.635.J 7\ Q TITLE ( NUMBER 2PL-NAFW Isolate AFW During Alternate Safe S/D STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.)
- 3. Candidate checks 3. Candidate checks hydraulic plunger hydraulic plunger full I out.[2FWE*HCV100A]
COMMENTS: I EVALUATOR CUE: Inform candidate that plunger is l'~N full out, about 6 inches. . kI i 4.C Switch the three- 4.C Candidate switches the position valve to three-position valve i CLOSE. to CLOSE. ) (2FWE*HCV100A] l
- EVALUATOR NOTE: Pointer-UP
. Handle pointing DOWN COMMENTS:
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A Page 2 of 9 Revision 0
RTL #AS.635.J LO J ( NUMBER TITLE , 2PL-NAFW Isolate AFW During Alternate Safe S/D STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.)
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5.C Insert handle onto pump 5.C Candidate insert's handle, handle onto pump handle. [2FWE*HCV100A] COMMENTS: 6.C Pump handle until valve 6.1.C Candidate pumps -( is closed. handle. (2FWE*HCV100A) 6.2.C Verify valve stem moving to CLOSE. [2FWE*HCV100A] EVALUATOR CUE: Inform candidate that valve stem moved to CLOSE position. COMMENTS: i-i
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RTL #AS.635.J e [ NUMBER TITLE 2PL-NAFW Isolate AFW During Alternate Safe S/D STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.) < 7.C Return the three- 7.C Candidate returns the position valve to three-position valve neutral. to NEUTRAL. [2FWE*HCV100A] COMMENTS:
',r- 8. Replace valve cover for 8. Candidate replaces 2FWE*HCV100A. cover for
( 2FWE*HCV100A. COMMENTS:
- 9. ' Remove valve cover for 9. Candidate removes 2FWE*HCV100B. cover from 2FWE*HCV100B.
I COMMENTS: Page 4 of 9 Revision 0
RTL /AS.635.J [ NUMBER TITLE 2PL-NAFW Isolate AFW During Alternate Safe S/D STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.) , 10 . . . . Candidate checks 10. Candidate checks hydraulic plunger hydraulic plunger full out. [2FWE*HCV100B] ! COMMENTS: ! l t EVALUATOR CUE: Inform candidate that plunger is NOT full out, only about 1 (.O inch. O Page 5 of 9 Revision 0
RTL #A5.635.J [ NUMBER TITLE 2PL-NAFW Isolate AFW During Alternate Safe S/D STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.) l 11.C Vent trapped pressure 11.1.C Candidate places 1/4 ball check valves. inch allen wrench into ! ball check set screws. l [2FWE*HCV100B] l I 11.2.C Slowly turns counter- ! clockwise until air is l Vented and plunger is ' observed to be full out. [2FNE'*HCV100B] -(9 EVALUATOP CUE: Trapped - pressure is relieved as indicated by plunger retracting to full out l position, about 6 inches. l i COMMENTS: 1 i Page 6 of 9 Revision 0
RTL #A5.635.J l f NUMBER TITLE 1 2PL-NAFW Isolate AFW During Alternate Safe S/D l STEP STANDARD - (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.) 12.C Retighten set screws. 12.C Candidate retightens set screws by turning to clockwise , direction. ) [2FWE*HCV100B) COMMENTS: l h 13.C Switch the three- 13.C , Candidate switches the 1 position valve to three-position valve CLOSE. to CLOSE. [2FWE*HCV100B] . COMMENTS: - 14.C Insert handle onto pump 14.C Candidate inserts handle. handle onto pump handle, j (2FWE*HCV100B] l COMMENTS: I Page 7 of 9 Revision 0
RTL #AS.635.J ! (-^ NUMBER TITLE 2PL-NAFW Isolate AFW During Alternate Safe S/D i i l STEP STANDARD (Indicate "S" for Sat. or "U" I ("C" denotes critical step) for Unsat.) j i 15.C Pump handle until valve 15.1.C Candidate pumps ! l is closed. handle. [2FWE*HCV100B] 15.2.C Verify valve stem moving to CLOSE. [2FWE*HCV100B] EVALUATOR CUE: Inform candidate that valve stem IS moving to CLOSE position. COMMENTS: 16.C Return the three- 16.C Candidate returns the position valve to three-position valve neutral. to NEUTRAL.[2FWE*HCV100B] i COMMENTS: . . I O Page 8 of 9 Revision 0
4 [ . 1 1 RTL #AS.635.J l l l(- NUMBER TITLE l 2PL-NAFW Isolate AFW During Alternate Safe S/D l STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.) i
- 17. Replace valve cover for 17. Candidate replaces 2FWE*HCV100B. cover for 2FWE*HCV100B.
COMMENTS: Stop Time: Page 9 of 9 Revision 0
? RTL #A5.635.J BVPS JOB PERFORMANCE MEASURE I ORAL QUESTION #1 During a small break LOCA, with AFW supplying feed to the S/Gs a feed break occurs on the "B" S/G aux feed line. The break is inside containment just downstream of aux feed to "B" S/G check valve [2FWE*100). For this situation, how would AFW pump 2FWE*P23B be protected against runnout? ANSWER: There is a cavitating venturi [2FWE*FE101B) that will limit flow to the S/G during a feed break, thus preventing runnout.. TIME 5 minutes ALLOTTED: KSA #: 061 K4.04 3.4 ( REF: 20M-24.1.E issue 4 rev. 1 page 6 OM 24 VONDS COMMENTS: I
i , RTL #AS.635.J BVPS JOB PERFORMANCE MEASURE f ORAL QUESTION #2 f( Tech Specs require a minimum of 127,000 gallons of water to be l in the Primary Plant demineralized Water Storage Tank during Modes 1, 2, and 3. What is the basis for this Tech Spec required water volume? ANSWER: Sufficient water is available to maintain the RCS at HOT STANDBY for 9 hours with steam discharge to atmosphere. TIME 2 minutes ALLOTTED: KSA #: 2.2.25 3.7 REF: T.S. bases 3/4.7.1.3 page B 3/4 7-2j (amend 85) . (- COMMENTS:
RTL #AS.635.J ' I' *
- THIS SHEET TO BE GIVEN TO CANDIDATE *
- BVPS JOB PERFORMANCE MEASURE l ORAL QUESTION #2 Tech Specs require a minimum of 127,000 gallons of water to be in the Primary Plant demineralized Water Storage Tank during Modes 1, 2, and 3. What is the basis for this Tech Spec required water volume? .
O I
RTL #A5.635.J !( *
- THIS SHEET TO BE GIVEN TO CANDIDATE *
- BVPS JOB PERFORMANCE MEASURE ORAL QUESTION #1 During a small break LOCA, with AFW supplying feed to the S/Gs a feed break occurs on the "B" S/G aux feed line. The break is inside containment just downstream of aux feed to "B" S/G check j valve [2FWE*100). For this situation, how would AFW pump i 2FWE*P23B be protected against runnout? l l
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RTL #A5.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE CANDIDATE DIRECTION SHEET
- THIS SHEET TO BE GIVEN TO CANDIDATE
- Read:
Task: Isolate AFW During Alternate Safe S/D l l INITIAL CONDITIONS: lAdeepseatedfirehasoccurredinthe cable spreading area just below the Control Room. The NSS has evacuated the l CR and activated the Alternate Shutdown ) Panel (ASP). Nuclear Operator #1 l Procedure 20M-56C.4.D has been completed I through step 10. "C" S/G AFW throttle I valves [2FWE*HCV100A & B) have been de- l energized. I l INIT. CUE: Your supervisor directs you to perform step 11 of Nuclear Operator #1 Procedure 20M-56C.4.D, and S report back when you have completed this step. At this time, ask the evaluator any questions you have on this l JPM. When. satisfied that you understand the assigned, task, announce "I am now beginning the JPM". Simulate performance or perform as directed the required task. Point to any indicator or component you verify or check and announce your observations. After determining the Task has been met, announce "I have completed the JPM". Then hand back this sheet to the evaluator. 1
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1 i i RTL #AS.640U BEAVER VALLEY JOB PERFORMANCE MEASURE i EVALUATOR COVER SHEET j- JPM Number: 2PL-050 Rev: la System #: 063
- JPM Titlel Place Spare Battery Charger 2-7 into Service.
1 4 K/A
Reference:
063K1.03 2.9/3.5 Task ID #: 0630070104 3 JPM Application: X NRC Initial Exam Training 1 f Evaluation Method LOCATION TYPE ! Perform Plant Site Training ! Simulate Simulator Annual Requal. Exam Classroom OJT j Initial Operator Exam l' Administered By: Other: BV-T NRC Other: l __ j Evaluation Results l Performer: Name: Employee No: Results SAT Time (minutes) [} UNSAT* Allotted: 20 Actual: Administrative JPM [3 Faulted [] Time Critical: Yes X No
- Comments (Required for UNSAT Evaluation):
i i ! Evaluation Results Check here if same as above l Observer 1: Name: Employee No: j Observer 2: Name Employee No:
- Observer 3
- Name Employee No:
! Observer 4: Name Employee No: Time (minutes) Results Question ID Allotted Actual SAT UNSAT* Question #1 [] [] Employee No: Question #2 []. [] Employee No:
- Comments (Required for UNSAT Evaluation):
O Evaluator (Print): Organization: Evaluator Signature: Date:
l l FTL #A5.6 5.J BEAVER VALLEY JOB PERFORMANCE MEASURE 1 ! l l EVALUATOR DIRECTION SHEET [\/ JPM NUMBER: 2PL-050 1 i JPM TITLE: Place' Spare Battery Charger 2-7 into Service l TASK ST7N.: BAT *2-2_is on an Equalizing charge via the spare charger. j RECOMMENDED
~ STARTING LOCATION: CONTROL ROOM l
1 DIRECTIONS: You are to simulate (perform) the task l Place Spare Battery Charger 2-7 into ' I Service l I INIT. CONDITIONS: The plant is at 100% power. The rectifier on UPS
- VITBUS 2-2 failed in the last 30 minutes. Vital Bus 2 has been transferred to REG *VITBS 2-2. BAT *2-2 has been checked, no water is required. Maintenance
,- has installed the spare battery charger [2-l\; 7) as a replacement for battery charger 2-
- 2. Battery charger 2-2 has been shutdown.
J The spare battery charger AC input and DC l output breakers are OPEN. I IT. CUE: The NSS has directed you to place the spare battery charger into service as a replacement for battery charger 2-2.
REFERENCES:
OM 2.39.4.D (issue 4 rev. 5 with OMCN 2 04) l TOOLS: DVM (simulated), Key 138 ' HANDOUT: OM 2.39.4.B l t l
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RTL #AS.635.J-' BVPS JOB PERFORMANCE MEASURE ORAL QUESTION #1 The' battery room exhaust. fans are OOS. What action (s) is/are required prior to battery room-entry? l ! ANSWER: The battery room should be checked with an explosimeter. l- TIME 2 minutes
- l. ALLOTTED:
KSA #: 063 K1.04 2.7 REF: 2OM-39.2A issue 4 rev. O P&L #12. Page 1. l-h COMMENTS: i l
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i i RTL #AS.635.J BVPS JOB PERFORMANCE MEASURE i ORAL QUESTION #2
'l \ What is the purpose of the Reactor Containment Penetration Backup Prot'ection Circuits (RCPBP), and briefly explain how they serventhis purpose. ,
I ANSWER: The Reactor Containment Penetration Backup Protection Circuits provide penetration short circuit protection. They sense overcurrent - faults at the penetration and will open when a fault occurs. TIME 4 minutes { ALLOTTED: KSA #: 063 K4.02 3.2 1 REF: 20M-37.1.B-issue 4 rev. O page 3 1st full ! paragraph. l COMMENTS: a i d Y as
RTL #AS.635.J J NUMBER TITLE ! 2PL-050 Place Spare Battery Charger 2-7 Into Service STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.) Start time:
- 1. Locate the procedure. 1.1 The candidate locates 20M-39.4.D.
COMMENTS:
^
i
- 2. Obtain key # 138 and a 2.1 Candidate simulates i
! DVM. obtaining key # 138 l [~h and a DVM. l &' EVALUATOR CUE: Use of the key and DVM will be ' simulated. L COMMENTS: ! 3.C Place battery charger 3.C Candidate places spare l power supply in battery charger L service. receptacle l [2PO*5002AC] to ON. l COMMENTS: I, J i,- " ! Page 1 of 8 Revision la
i RTL #A5.635.J [vl NUMBER TITLE 2PL-050 Place Spare Battery Charger 2-7.Into Service STEP- STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.) . 4.C Energize battery 4.C The candidate places charger receptacle. Spare battery charger receptacle power supply (MCC*2-E08'(BKR 5B)] to ON COMMENTS:
,\ \ ,) 'E'ALUATOR V CUE: Another operator has verified
[MCC*2-E08 (BKR SB)] ON EVALUATOR CUE: Wire ties and tie wraps have all been previously removed. O Page 2 of 8 Revision la
RTL #A5.635.J , NUMBER TITLE 2PL-050 Place Spare Battery Charger 2-7 Into Service i STEP STANDARD j (Indicate "S" for Sat. or "U" ' ("C" denotes critical step) for Unsat ) l' 5.C Energize battery 5.1.C The candidate places l l charger. Spare battery-charger j receptacle ' [2PO*5002DC) to ON 5.2. The candidate requests a second verification for this step. j COMMENTS: O lV
)
l EVALUATOR CUE: Role play the supervisor and inform candidate that you will have another operator perform the second verification. ! ) l-O Page 3 of 8 Revision la t l
RTL #A5.635.J NUMBER TITLE [) 2PL-050 Place Spare Battery Charger 2-7 Into Service l ! STEP STANDARD i (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.) 6.C Place the battery 6.C The candidate places charger to FLOAT. the Float / Equalize switch to FLOAT. COMMENTS: 7 Ensure the timer is set 7 Candidate simulates to zero, turning the timer to (-
\
zero position.
]
i COMMENTS: l I i I i l l l
- O i
i Page 4 of 8 Revision la
RTL #AS.635.J NUMBER TITLE 2PL-050 Place Spare Battery Charger 2-7 Into Service STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.) 8 Check closed battery 8.1 The candidate checks-breaker. battery breaker [ BAT *BKR2-2] CLOSED. 8.2. The candidate requests a second verification for this step. EVALUATOR CUE:-Role play the supervisor and inform
/~' candidate that you will
(_)h have another operator , I perform the second verification. l l COMMENTS: 9.C Place'the DC output 9.C The candidate places breaker to ON the DC output breaker at [ BAT *CHG2-7] to ON COMMENTS: O f. Page 5 of 8 Revision la
RTL #A5.635.J
.fm Q NUMBER TITLE 2PL-050 Place Spare Battery Charger 2-7 Into Service STEP STANDARD (Indicate "S" for Sat. or "U"
("C" denotes critical step) for Unsat.) 10.C Place the AC input 10.C Candidate places the breaker.to ON .AC input breaker at [ BAT *CHG2-7) to ON COMMENTS: -
-11.- Ensure AC ON light is 11. Candidate verifies AC lit. ON light at'[ BAT *CHG2- .- O '7) is lit.
COMMENTS: EVALUATOR CUE: AC ON light at (BAT *CHG2-7] is lit. Page 6 of 8 Revision la
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i RTL fAS.635.J t 8 NUMBER. TITLE 2PL-050' Place Spare Battery Charger 2-7 Into Service STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.)
- 12. Ensure current output 12. Candidate verifies l is positive. ammeter at [ BAT *CHG2-
- 7) is indicating positive amperage.
COMMENTS: ,, EVALUATOR CUE: Amps are O
} positive 55.
EVALUATOR CUE: I.f , candidate asks what the output voltage is at this point, cue that it is 130.6 volts. This will force the l candidate to perform steps i t 13 and 14 of the JPM. l
- 13. Connect a DVM across 13.1 Candidate simulates j the terminals of the connecting the leads voltmeter. of the DVM to the leads of the voltmeter.
13.2 Verifies DVM selected ! to AUTO range. COMMENTS: p
- V 4
Page 7 of 8 Revision la i
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RTL #A5.635.J l l [ml'
\~J NUMBER TITLE r
L 2PL-050 Place Spare Battery Charger 2-7 Into l Service j STEP STANDARD l (Indicate "S" for Sat. or "U" L ("C" denotes critical step) for Unsat.) 14 Adjust float voltage to 14.1 Candidate checks DVM i obtain 134.5 to 135.5 voltage reading. VDC. EVALUATOR CUE: Volts are 130.6. , 14.2 Candidate simulates l turning voltage adjust potentiometer clockwise to raise voltage. 'O
- EVALUATOR CUE: Volts are j 135.0. !
l 14.3 Candidate checks i l charger' output I amperage. EVALUATOR CUE: Amps are j positive 53. I COMMENTS: I Stop Time: i l i i - .,l l l Page 8 of 8 Revision la l
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- l- RTL #A5.635.J
*
- THIS SHEET TO BE GIVEN TO CANDIDATE *
- 1 BVPS JOB PERFORMANCE MEASURE ORAL QUESTION #2 l
What is the purpose of the Reactor Containment Penetration l Backup Protection Circuits, and briefly explain how they serve this purpose. I l . l l l I 1 l
's 1
4 i i 4 3 e l-l- l l l \ {. l.
4
-RTL #A5.635.J 1
1 *
- THIS SHEET TO BE GIVEN TO CANDIDATE *
- i
+
% l 1
v. l l BVPS JOB PERFORMANCE MEASURE- i s- .
; ORAL QUESTION #1 l 1 ; The battery room exhaust' fans are OOS. What action (s) is/are a
1 required prior to battery room entry? 4 1 a 4 d t, 2 i i i' t l- -4 . . !, O e e d a i 4 Y e I. 1'. ( 4 J
, 1 1
i
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l kTL #AS.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE CANDIDATE DIRECTION SHEET /~% ! ()
- THIS SHEET TO BE GIVEN TO CANDIDATE
- Read:
Task: lPlaceSpareBatteryCharger2-7 into Service. l l i l l INITIAL CONDITIONS: lTheplantisat100% power. The l rectifier on UPS
- VITBUS 2-2 failed in j the last 30 minutes. Vital Bus 2 has .
been transferred to REG *VITBS 2-2. BAT *2-2 has been checked, no water is I required. Maintenance has installed the I spare battery charger [2-7] as a j replacement for battery charger 2-2. 1 Battery charger 2-2 has been shutdown. The spare battery charger AC input and DC output breakers.are OPEN. ! /~' N-gI : 1 INIT. CUE: The NSS has directed you to place the spare battery. charger into service as a replacement for battery charger 2-2. At this time, ask the evaluator any questions you have on this JPM. When satisfied that you understand the assigned task, announce "I am now beginning the JPM". Simulate performance or perform as directed the required task. Point to any indicator or component you verify or check and announce your observations. After determining the Task has been met, announce "I have completed the JPM". Then hand back this sheet to the evaluator, rh U
i , RTL #AS.640U BEAVER VALLEY JOB PERFORMANCE MEASURE EVALUATOR COVER SHEET l JPM Number: 2PL-047 Rev: 2a System #: 028 Faulted: ! JPM
Title:
Locally Startup Containment Hydrogen Analyzer [2HCS*HA100A]. ! K/A
Reference:
028000A4.01 4.0/4.0 Task ID #: 028AAA0104 JPM Application: X Requal X Initial Exam Training i i Evaluation Method LOCATION TYPE f [] Perform Plant Site Training f Simulate [3 Simulator Annual Requal. Exam ! [3 Classroom OJT s j Initial Operator Exam o Administered By: Other: j [] BV-T NRC 4 Other: l Evaluation Results Performer: Name: Employee No: l l Results SAT Time (minutes) l UNSAT* Allotted: 15 Actual: l Time Critical: Yes x No f Administrative JPM Faulted [3 l
- Comments (Required for UNSAT Evaluation):
I i - i Evaluation Results Check here if same as above Observer 1: Name: Employee No: Observer 2: Name Employee No: Observer 3: Name Employee No: Observer 4: Name Employee No: Time (minutes) Results Question ID Allotted Actual SAT UNSAT* Question #1 Employee No: Question #2 Employee No:
- Comments (Required for UNSAT Evaluation):
k Evaluator (Print): Organization: Evaluator Signature Date:
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i ! RIL #A5.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE
/~* EVALUATOR DIRECTION SHEET U
I JPM NUMBER: 2PL-047 JPM TITLE: Locally Startup Containment Hydrogen Analyzer [2HCS*HA100A).
*I H2 Analyzer is in service ready to obtain samples.
l i RECOMMENDED STARTING LOCATION: CONTROL ROOM DIRECTIONS: You are to simulate (perform) the task Locally Startup Containment Hydrogen Analyzer [2HCS*HA100A) INIT. CONDITIONS: The plant is in Mode 1. Containment Hydrogen Analyzer [2HCS*HA100A] is OOS for maintenance. Maintenance has completed repairs on the analyzer. As part of their final calibration, maintenance requests i[, / -sh that you locally start Containment Hydrogen i Analyzer [2HCS*HA100A). The analyzer cabinet has already been energized. IN . CUE: Your supervisor directs you to locally startup Containment Hydrogen Analyzer [2HCS*HA100A] and report back when it is in operation.
REFERENCES:
OM-2.46.4.F Issue 4 Revision l' TOOLS: None i j HANDOUT: OM-2.46.4.F I l
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l l '~' NUMBER TITLE-l 2PL-047 Locally Startup the Containment H2 Analyzers . STEP STANDARD (Indicate "S" for Sat. or "U" l ("C" denotes critical step) for Unsat.) . Start time:
- 1. Obtain procedure. 1. Candidate obtains Procedure 2OM-46.4.F.
COMMENTS: 2.C At the control panel Candidate enters Pre-
,\ LOCA heat trace
('
'N l enter Pre-LOCA heat trace values. values.
2.1.C Monitor Mode 6 Access Code 82, ENTER ~ Select change 3 Select cal. array element 1618, ENTER Select PRE-LOCA
- setpt 896,NXT Select Change 3 Select cal. array element 1518, ENTER Select PRE-LOCA retpt 896,NXT COMMENTS:
EVALUATOR CUE: All control ! panel data has been entered successfully. (/ i Page 1 of 3 Revision 2a i
l l RTL #AS.635.J A / NUMBER TITLE l 2PL-047 Locally Startup the Containment H2 Analyzers STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.) 3.C Open containment 3.C Candidate contacts CR isolation valves (VB and requests opening
'A') of valves:
-- 2HCS*SOV133A -- 2HCS*SOV133A
-- 2HCS*SOV134A -- 2HCS*SOV134A
-- 2HCS*SOV136A -- 2HCS*SOV136A
-- 2HCS*SOV136B -- 2HCS*SOV136B EVALUATOR CUE: All valves listed have only the red l [')
. .Q,) light illuminated. 7 COMMENTS: I 4.C At the H2 Analyzer 4.C Candidate locates the Remote Control Panel Power Control Switch j (2HCS*PNL100A) place on 2HCS*PNL100A and the Power Control indicates that he/she Switch to ON. would place it in the "ON" position. EVALUATOR CUE: Power was already ON from initiating cue. Power "ON" is indicated. COMMENTS: q,. Page 2 of 3 Revision 2a
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RTL #AS.635.J i (-- NUMBER TITLE 2PL-047 Locally Startup the Containment H2 Analyzers l STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.) l 4.C At the H2 Analyzer 4.1.C- Candidate ~ locates the Remote Control Panel Pump Control Switch on j ( 2HCS*PNL100A) 2HCS*PNL100A and ' momentarily place the indicates that he/she l Pump Control Switch to would momentarily l START. place it to the START position. 4.2 Candidate verifies red light illuminated. (\ EVALUATOR CUE: Pump is in
' (_) . operation.
illuminated. Red light
~
4.3 Verify the following lights ON SV-1 SV-6 COMMENTS: , EVALUATOR CUE: Lights are LIT EVALUATOR CUE: It is r,ot desired to start the recorder at this time. Stop Time:
/]
NJ Page 3 of 3 Revision 2a
73 RTL #AS.635.J BVPS JOB PERFORMANCE MEASURE (b ORAL QUESTION #1 What are five sources of hydrogen gas accumulation within the Containment following a loss of coolant accident? ANSWER: 1. Metal - water reaction between the zirconium fuel cladding and the reactor coolant.
- 2. Pressurizer gas space and RCS water-
- 3. Radiolytic decomposition of water collected on the containment floor with a corresponding generation of oxygen.
- 4. Radiolytic decomposition of water in the reactor core.
- 5. Corrosion of metals by solutions used for emergency cooling or containment spray.
TIME 5 minutes ALLOTTED: KSA #: G28KS.01 3.4/3.9 Rev.1
/~') 028000K5.01 3.4/3.9
- v REF: OM-2.46.1. Summary Description p 1 of 3.(Issue 1 rev. 5)
COMMENTS: I 1 I l l l h v I i r I
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i 1 RTL #A5.635.J BVPS JOB PERFORMANCE MEASURE f S ORAL QUESTION #2 i
' .k'~') - Unit 2 has been operating at 100% power with one gydrogen g analyzer out of service for 29 days. On this 29 day the .l second hydrogen analyzer is declared inoperable. Neither one i of the hydrogen analyzers will be returned to service soon.
What action must be taken and by what time frame? ANSWER: Restore to operable within 72 hours or be in HOT STANDBY within the following 12 hours. 1 TIME 3 minutes ALLOTTED: KSA #: 028000G11 2.9/3.5 2.1.12 2.9/4.0 Rev. 1 REF: T.S. 3.6.4.1 Hydrogen Analyzers COMMENTS: O e r i
-RTL #A5.635.J-I ,
I.* l ( *
- THIS SHEET TO BE GIVEN TO CANDIDATE *
- i l BVPS JOB PERFORMANCE MEASURE ,
ORAL QUESTION #1 What are five sources of hydrogen, gas accumulation within the
- Containment following a loss of coolant accident?
r e l i O . O l I I. t ! l i A s' 4
RTL #AS.635.J Lo [-
*
- THIS SHEET TO BE GIVEN TO CANDIDATE *
- q l
BVPS JOB PERFORMANCE MEASURE l ORAL QUESTION #2 Unit 2 has been operating at 100% power with onegydrogen analyzer out of service for 29 days. On this 29 day the second hydrogen analyzer is declared inoperable. Neither'one of the hydrogen analyzers will be returned to service soon. What action must be taken and by what time frame? I i l d r
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l i ? l' l. iO I i l- - -
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I RTL #A5.635.J BEAVER VALLEY JOB' PERFORMANCE MEASURE CANDIDATE DIRECTION SHEET i [ L
- THIS SHEET TO BE GIVEN TO CANDIDATE * ,
i
' Read: 3 j Task: Locally Startup Containment Hydrogen ,
Analyzer [2HCS*HA100A).. i i L INITIAL' CONDITIONS: lTheplantisinMode'1. Containment ' Hydrogen Analyzer [2HCS*HA100A] is OOS for maintenance. Maintenance has completed ; repairs on the analyzer. As part of their final calibration, maintenance requests. l that you locally start Containment. 4 Hydrogen Analyzer [2HCS*HA100A). The analyzer cabinet has already been , energized.
) INIT. CUE: Your supervisor directs you to locally startup Containment Hydrogen Analyzer [2HCS*HA100A] and '
report back when it is in operation. i L At this time, ask the evaluator any questions you have on this j JPM.. l
--~
When satisfied that you understand the assigned task, announce "I am now beginning the JPM". Simulate' performance or perform as directed the required task. i Point to any-indicator or component you verify or check and i announce your observations. After determining.the Task has been met, announce "I have ! completed the JPM". Then hand back this sheet to the evaluator. , l' ! l 1 l ? . f . >sz,V) < r
]
s
v (~~) V ES-301 Administrative Topics Outline Form ES 301-1 Facility: _ Beaver Vallev Power Station Unit 2 Date of Examination: _8/17/98 Examination Level (circle one): RO / SRO Operating Test Number: 2 LOT 2A Administrative Describe method of evaluation: Topic / Subject 1. ONE Administrative JPM, OR Description 2. TWO Administrative Questions A.1 Plant Parameter Bank JPM 2CR-017 - Shutdown Margin Verification Response & New JPM - 1/20M-48.1.H Notification for - Potential Tampering A.2 Survelilance 01 - What are the specific additionaladministrative Testing requirements for tagging out a D/G in Mode 1
/\
U (New) Q2 - Tech Spec 3.06 application (New) , 1
< l A.3 Approve New JPM - Emergency Exposure Control Emergency ,
' Exposure l l
l Protective Action New JPM -PAR A.4 Recommendct,ons i e'~'N V NUREG-1021 1 of 1 Interim Rev. 8, January 1997 BVPS 2 LOT 2A Revision 1
1 . _,, r lO l CHANGES TO ADMINISTRATIVE TOPICS OUTLINE NOTE: All changes to the original outline are in BOLD /TAL/CS on the revision 1 ' l outline. P
- 1. Question # 1 of Topic A.2 was changed to an ESF checklist question. The
- PMT question that was originally int' ended is no longer the responsibility of , ,
the NSS, rather this responsibility has been delegated to the new Work ; 1 Control center, as part of an effort to eliminate the administrative burden on t the NSS.
}
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- .. _. - _. - . _ _ _ - . - _ ~ - - . - _ _ . . . . - - - . _ - . . - - - - . . _ _ _ - - - - - - - . . ~ _ - - RTL #AS.640.U BEAVER VALLEY JOB PERFCRMANCE MEASURE l EVALUATOR COVER SHEET JPM Number: 2CR-017 Rev: 3a System #: 001 I JPM
Title:
Perform a Shutdown Margin calculation K/A
Reference:
192002K1.13 3.5/3.7 Task ID #:0010040101 005 AK1.05 3.3/4.1 JPM Application: X Requal X Initial Exam O Training Evaluation Method LOCATION TYPE O Perform O Plant Site O Training 0 l Simulate O Simulator O Annual Requal. Exam ) O Classroom O Oar O Initial Operator Exam , Administered By: O Other: O Bv-T O NRC O Other: l l Evaluation Results l A Performer: Name: Employee No: D Results O SAT Time (minutes) O UNSAT* Allotted: 10 Actual: Time Critical: Oyes X No ' Administrative JPM: X Faulted: O l
- Comments (Required for UNSAT Evaluation):
I Evaluation Results O Check here if same as above ! Observer 1: Name: Employee No: l Observer 2: Name Employee No: , Observer 3: Name Employee No: ' observer 4: Name Employee No: Time (minutes) Results Question ID Allotted Actual SAT UNSAT* Question #1 O O Employee No: Question #2 O O Employee No:
- Comments (Required for UNSAT Evaluation):
O Evaluator (Print): Organization: Evaluator Signature Date: I
s RIL #AS.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE
/~ EVALUATOR DIRECTION SHEET
[ '% JPM NUMBER: 2CR-017 JPM TITLE: Perform a Shutdown Margin Calculation A STAN.: The shutdown margin calculation is. complete and a correct determination is made when the results are compared to the acceptance criteria. RECOMMENDED STARTING LOCATION: CONTROL ROOM DIRECTIONS: You are to simulate (perform) the task Perform Shutdown Margin Calculation. INIT. CONDITIONS: The plant is at 100% power BOL.,One rod is inoperable (immovable and untrippable). All rods are fully withdrawn. The core is at Beginning-Of-Life with a boron , /"% concentration of 1200 ppm. The " Initial Js Conditions" of the OST are met. I T. CUE: Your supervisor directs you to perform a shutdown margin calculation and determine if the acceptance criteria is met.
REFERENCES:
Tech Specs 20ST-49.1 Issue 4 Revision 1 TOOLS: Calculator HANDOUT: 2OST-49.1 f
\_/
l i
l RTL #AS.635.J l l 'f^%t I l '- NUMBER TITLE ! 2CR-017 Perform a Shutdown Margin Calculation l STEP STANDARD l (Indicate "S" for Sat. or "U" j ("C" denotes critical step) for Unsat.) Start time:
- 1. Obtain shutdown margin 1. Candidate locates form. 20ST-49.1 l
EXAMINER CUE: The examiner should give the candidate the form after he/she has shown the he/she can find 'g73 3 it, wJ EXAMINER NOTE: Allow the candidate to calculate the shutdown margin and then j review the results. A ! reasonable margin of error l (math and graph interpretation) is allowed i as long as the method is ; correct. If the simulator is not I being used cue as needed j that the plant is at 100% i ! and Rods are at 227 steps on CB "D". The Sample Data Sheet may used to compare results. , l l i (fg COMMENTS:
-Page 1 of 4 Revision 3a -
s-RTL #AS.635.J NUMBER TITLE (. 2CR-017 Perform a Shutdown Margin calculation STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.)
- 2. Determine Initial Test 2.1 Candidate records the Prep Data. following data on step A.1 Control Bank D steps (227).
Power level (100%) Boron concentration (1200 ppm). Number of untrippable rods as(1) O COMMENTS:
- 3. Calculate the 3. Candidate completes reactivity worth of the Step B.1:
rods.
-All rods are 227
-Bank Worth is 7.362
-Integral Worth is 0
-TBW is 7.362.
-90% Uncertainty is l 6.6258. i l
COMMENTS: .
- 4. Determines Power Defect 4. Candid, ate determines for current boron power defect from concentration and power Figure 1 (between 1.54 i level, and 1.58) enters value 1 on step B.2.
O k-s COMMENTS: l Page 2 of 4 Revision 3a -
5 e i l RTL #A5.635.J l I A) l(
~! NUMBER TITLE 2CR-017 Perform a Shutdown Margin Calculation l
l l STEP STANDARD (Indicate "S" for S'at. or "U" ("C" denotes critical step) for Unsat.)
- 5. Enter stuck rod worth. 5. ?)andidate calculates the worth of the stuck / immovable rods.
Adds 1 to A.4 (2) and multiplies by 1.322%. Enters 2.644 on Step B.3
~
\
l.(V COMMENTS: P
- 6. Calculates the Shutdown 6. Candidate calculates Margin, the Shutdown Margin.
Subtracts' Power Defect (1.54 to 1.58) and Stuck Rod Worth (2.644) from 90% Total Bank Worth (6.6258) Enters value on Step B.4 (range 2.4018-2.4418) COMMENTS: I l
- I l
b Page 3 of 4 Revision 3a -
RTL #A5'.635.J
.t f')
lsj NUMBER TITLE 2CR-017 Perform a Shutdown Margin Calculation STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.) ! 7.C Determine if SDM is 7.1 Candidate compares adequate. calculated SDM to Acceptance Criteria. 7.2.C Candidate' verifies that value of the SDM calculated (2.4**) is 2 to the Acceptance Criteria (1.77):
- N._/ 7.3 Informs supervisor of SAT test completion.
7.4 Completes the OST . cover. COMMENTS: EXAMINER NOTE: The last two { substeps may be omitted. _ Stop Time: D. U-Page 4 of 4 Revision 3a -
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RTL #AS. 635.J BEAVER VALLEY JOB PERFORMANCE MEASURE g CANDIDATE DIRECTION SHEET ' '~/
- THIS SHEET TO BE GIVEN TO CANDIDATE
- t Read:
Task: lPerformaShutdownMarginCalculation INITIAL CONDITIONS: The plant is at 100% power BOL. One rod is inoperable (immovable and untrippable). All rods are fully withdrawn. The core is at Beginning-Of-Life with a boron concentration of 1200 ppm. The " Initial Conditions" of the OST are met. INIT. CUE: Your supervisor directs you to perferm a shutdown
/" margin calculation and determine if 6.he acceptance (s,T
/ criteria is met.
At this time, ask the evaluator any questions you have on this JPM. When. satisfied that you understand.the assigned task, announce "I am now beginning the JPM". Simulate performance or perform as directed the' required task. Point to any indicator or component you verify or check and announce your observations. After determining the Task has been met, announce "I have completed the JPM". Then hand back this sheet to the evaluator.
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- RTL #AS.640.U BEAVER VALLEY JOB PERFORMANCE MEASURE j EVALUATOR COVER SHEET JPM Number
- Adm-Tamper Rev: O System #: 2.4 JPM
Title:
Response & Notification to Potential Tampering or Mispositioning Event f i K/A
Reference:
2.4.28 2.3/3.3 Task ID #:344JJJ0302 1 6 JPM Application: X Requal X Initial Exam O Training Evaluation Method LOCATION TYPE i Perform O Plant Site Training Simulate Simulator Annual Requal. Exam l j O Classroom OJT l Initial Operator Exam t Administered By: Other: 1 O av-T 1 j NRC l 0 Other: i - { I Evaluation Results Performer: Name: Employee No: Results O SAT Time (minutes) O UNSAT* Allotted: 10 Actual: , Time Critical: Oves x No Administrative JPM: E Faulted:
- Comments-(Required for UNSAT Evaluation):
Evaluation Results O Check here if same as above Observer 1: Name: Employee No: Observer 2: Name Employee No: Observer 3: Name Employee No: Observer 4: Name Employee No: Time (minutes) Results Question ID Allotted Actual SAT UNSAT* Question #1 O Employee No: Question #2 O Employee No:
- Comments (Required for UNSAT Evaluation):
O Evaluator (Print): Organization: . Evaluator Signature Date:
GP RIL #A5.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE EVALUATOR DIRECTION SHEET JPM NUMBER: Adm-Tamper JPM TITLE: Response & Notification to Potential Tampering or Mispositioning Event TASK STAN.. Implement 1/2OM-48.1.H, and Notify. Security, Plant Management, and initiate a CR RECOMMENDED STARTING LOCATION: CONTROL ROOM DIRECTIONS: You are to simulate (perform) the task Response & Notification to Potential Tampering Event INIT. CONDITIONS: The plant is at 100% power, all systems in NSA. "A" HHSI pump is running with "B" HHSI pump in Standby. "C" HHSI pump is unavailable. The PAB operator has called to f-~ report that the service water supply valve to the "B" HHSI pump lube oil cooler . ( ') i [2SWS*164) is locked SHUT. He thinks it should be locked.OPEN. There have been NO maintenance activities, or OST's run on ' either service water or the HHSI pumps in the last 30 days. I *
- As the NSS you are to respond to this report by implementing the appropriate administrative procedure.
REFERENCES:
1/2OM-48.1.H issue 4 rev. O l TOOLS: HANDOUT: 1/20M-48.1.H issue 4 rev. 0
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RTL #AS.635.J f TITLE NUMBER ADM-Tamper Response & Notification to Potential Tampering or Mispositioning Event STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.) Start time: EXAMINER NOTE: Candidate may reference NPDAP 5.9
" Reporting & Notification of Potential Tampering or Mispositioning Event" before locating procedure.
NPDAP 5.9 will instruct the
/~' candidate to reference to
( implement Procedure 1/20M-
- l. 48.1.H.
- 1. Obtain Procedure 1. Candidate locates '
Procedure 1/2OM-48.1.H
- 2. Dispatch an operator 2. Contact PAB operator, to limit access and instruct to limit leave valve as found, access and leave valve j as found. ,
1 l l EXAMINER CUE: Role play PAB operator. You will limit access and leave valve as found. 1 I COMMENTS: l l Page 1 of 4 Revision 0 l
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RTL #AS.635.J
/"% ,.' r NUMBER TITLE ADM-Tamper Response & Notification to Potential Tampering or Mispositioning Event STEP STANDARD (Indicate "S" for Sat. or "U"
("C" denotes critical step) for Unsat.) 3.C Utilize figure 48.1.H-1 3.1 Candidat'e should use to determine figure 48.1.H-1 to appropriate level of answer the following required actions and questions: notifications. 3.2 Does this involve a locked component? (
,\.D>
4 EXAMINER NOTE: Answer should be YES 3.3 Is there evidence of recent work history? EXAMINER NOTE: Answer should be NO (from initial conditions). 3.4 Is there evidence of recent operations I history? l . EXAMINER NOTE: Answer
.[~ ) should be NO (from initial !
l \_/ conditions). Page 2 of 4 Revision 0 I I
l RTL #A5.635.J lO INUMBER TITLE ADM-Tamper Response & Notification to Potential Tampering or Mispositioning Event l STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.) - I l 3.5 Is the event l explainable? l l t r l EXAMINER NOTE: Answer should be NO (from initial conditions there is no evidence to support a yes answer). V( \- 3.6.C- NSS determines that I Security supervisor must be notified, and
- l contacts security supervisor.
EXAMINER CUE: Role play Security supervisor and accept notification.
.3.7.C NSS determines that i
Plant Management must be notified, and l contacts Plant Management s ! EXAMINER CUE: Role play Plant Management and accept l(g notification.
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Page 3 of 4 Revision 0
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? L-RTL #A5.635.J , O NUMBER TITLE ADM-Tamper Response & Notification to Potential Tampering or Mispositioning Event i STEP STANDARD (Indicate "S" for Sat. or "U" l ("C" denotes critical step) for Unsat.) 3 . 8 . C, NSS determines that a Condition Report must be initiated, and initiates a Condition Report. EXAMINER CUE: Inform candidate that it is not necessary to fill out the condition report at this L[~_' time. N- 4 1 I
- 4. Utilize the Safeguards 4. NSS and Operations -
equipment operability management will begin checklists. discussing use and extent of Safeguards ; equipment operability l I checklists. EXAMINER CUE: Inform l candidate that it is not necessary to determine which checklists will be implemented for ,this JPM I COMMENTS: I Stop Time: o I Page 4 of 4 Revision 0 l t-
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RTL #AS.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE
,_ CANDIDATE DIRECTION SHEET
'd
- THIS SHEET TO BE GIVEN TO CANDIDATE
- j Read:
i i Task: l Response &NotificationtoPotentialTamperingor i Mispositioning Event l
~
i INITIAL CONDITIONS: The plant is at 100% power, all systems in NSA. "A" HHSI pump is running with "B" HHSI pump in Standby. "C" HHSI pump is unavailable. The PAB operator has called to report that the service. water supply valve to the "B" HHSI pump lube oil l cooler [2SWS*164) is locked SHUT. He thinks it should be locked OPEN. There have been NO maintenance activities, or OST's run on either service water or the
~ . HHSI pumps in the last 30 days.
INIT. CUE: As the NSS you are to respond to this report by implementing the appropriate administrative , procedure. At this time, ask the evaluator any questions you have on this JPM. When satisfied that you understand the assigned task, announce "I am now beginning the JPM". Simulate performance or perform as directed the required task. Point to any indicator or component you verify or check and announce your observations. After determining the Task has been met, announce "I have completed the JPM". Then hand back this sheet to the
' evaluator.
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J ( RTL #A5.635.J BVPS JOB PERFORMANCE MEASURE Topic A.2. surveillance Testing Question # 1 The plant is in Mode 1, with All systems in NSA. A PMP is due.to change the fuel oil filter on the #2. Diesel. The PRA'has been completed and the risk is within acceptable limits. The GMNO has approved the performance of this PMP.
- What SPECIFIC additional administrative actions are required to be performed as part of the Clearance /Tagout to ensure operability of redundant train components.
ANSWER: NOTE:
.r~ This question is surrounding the ESF checklist. ; '4' ,g/ The candidate may discuss numerous other '
administrative requirements.
- 1. Verify'2FWE*P22 operability. , ,
- 2. Verify no thunderstorm or tornado watches.
- 3. Verify BOTH UNIT 1 D/Gs operable. ,
- 4. TS 3.8.1.1 actions completed within 1 hour PRIOR to removal. l
. TIME -
5 minutes ALLOTTED: KSA./: 2.2.13 3.8
.REF: NPDAP 3.4 attachment 5 item 8 page 3 rev. 9 COMMENTS:
O Revision 0
iV RTL #A5.635.J BVPS JOB PERFORMANCE MEASURE Topic A.2 Surveillance Testing Question # 2 The plant is operating at 100% power all systems in NSA except 2RCS*PT455 PZR Pressure transmitter has been OOS for the past 30 days. ALL Tech Spec required bistables have been placed in their tripped condition. I&C informs you that 2RCS*PT456 PZR Pressure transmitter was due for its functional test (MSP) 22.75 days ago. Briefly discuss what Tech spec actions will be required to perform the functional test for 2RCS*PT456 PZR Pressure transmitter. Include any applicable time limits. ANSWER: (per TS 3.0.6 and its bases) Under administrative control, the bistables for 2RCS*PT455 PZR Pressure transmitter may be untripped (to perform testing on 2RCS*PT456 PZR Pressure transmitter). The allowable time for s having the bistables for 2RCS*PT455 PZR Pressure
) trarsmitter untripped MUST be limited to that time ABSOLUTELY necessary to perform the testing.
~
NOTE: The 30 days and 22.75 days in the question, are there to force the student to realize that the allowable 25% extension for the 92 day required frequency (23 days) for the functional testing is about to expire. TIME 10 minutes ALLOTTED: KSA #: 2.1.12 4.0 REF: Tech Spec 3.0.6 and bases I COMMENTS: ^v Revision 0 1.
RTL #A5.635.J BVPS JOB PERFORMANCE MEASURE Topic A.2 Surveillance Testing Question # 2 The plant is operating at 100% power all systems in NSA except 2RCS*PT455 PZR Pressure transmitter has been OOS for the past 30 days. ALL Tech Spec required bistables have been placed in their tripped condition. I&C informs you that 2RCS*PT456 PZR Pressure transmitter was due for its functional test (MSP) 22.75 days ago. Briefly discuss what Tech spec actions will be required to perform the functional test for 2RCS*PT456 PZR Pressure transmitter. Include any applicable time limits. 'i
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9 (T ! LJ Revision 0 3
RTL #AS.635.J BVPS JOB PERFORMANCE MEASURE
}
Topic A.2 Surveillance Testing Question # 1 The plant is in Mode 1, with All systems in NSA. A PMP is due to change the fuel oil filter on the #2 Diesel. The PRA has been completed and the risk is within acceptable limits. The GMNO has approved the performance of this PMP. What SPECIFIC additional administrative actions are required to be performed as part of the clearance /Tagout to ensure operability of redundant train components. i l l ' l O 4 6 I i Revision 0
9-- -m BEAVER VALLEY JOB PERFORMANCE MEASURE EVALUATOR COVER SHEET JPM Nunmer: ADM-Emer Ex Rev:0 System #: 2.3 ( JPM
Title:
Determine Emergency Exposure Limit K/A
Reference:
2.3.4 (3.11 Task ID #: 343 029 0302 JPM Application: ' Requal X Initial Exam E3 Training Evaluation Method LOCATION TYPE X Perform E3 Plant Site Training E Simulate (3 Simulator E3 Annual Requal. Exam b Classroom E OJT Ud Initial Operator Exam Administered By: E3 Other: BV-T X NRC Other: Evaluation Results
! Performer: Name: Employee No:
Results [3 SAT Time (minutes) e B UNSAT* Allotted: 20- Actual: Time Critical: E Yes X No Administrative JPM X Faulted E3
- Comments (Required for UNSAT Evaluttion):
Evaluation Results E Check here if same as above Observer 1: Name: Employee No: Observer 2: Name Employee No; observer 3: Name Employee No: Observer 4: Namc Employee No: Time (minutes) Results Question ID Allotted Actual SAT UNSAT* Question #1 N/A g Employee No: , Question #1 N/A [] Employee No:
- Comments (Required for UNSAT Evaluation):
Evaluator (Print): Organization; Evaluator Signature Date:
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i
'EUL #A5.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE /~' EVALUATOR DIRECTION SHEET (Y
JPM NUMBER: ADM-Emer Ex JPM TITLE: Determine Emergency Exposure Limit TASK STAN: Determine the maximum allowable limits for emergency exposure. RECOMMENDED Control Room / Simulator STARTING LOCATION: i DIRECTIONS: Determine maximum allowable limits for emergency exposure. ! INIT. CONDITIONS: - An Alert has been declared at Unit 2 due to LOCA. An, operator has slipped an fallen in the VCT cubicle while troubleshooting erratic VCT-level indications. The operator is bleeding profusely, from the' scalp. . Health Physics has determined extremely high radiation exists in ; the VCT cubicle. The emergency squad believes ! t/~sg s ) the individual will bleed to death if he
.doesn' t receive prompt medical attention. The i
Unit 1 ANSS has volunteered to enter the VCT l cubicle to extract the victim. His Rad worker ' qualifications'are current for BVPS and Rad con supervision has briefed him on the risks associated with his projected dose for the 1 l extraction of the operator from the VCT cubicle. Jim Cross (Duquesne Light Chief Nuclear Officer) has been briefed of the i situation and has NOT, and WILL NOT authorize l additional exposures. l 'INIT. CUE: You are th' Emergency Director. Determine the emergency exposure limitation for ,the Unit 1
.ANSS to perform this extraction. ]
l < !
- EPP/IP 5.3, Rev. 7 j RE FERENCES.
- .
- TOOLS: None l
b LHANDOUT:
/
', ( 7 i
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A RTL'#AS.635.J ,
;I '
( NUMBER TITLE ADM-Emer Ex Determine Emergency Exposure Liniit l STEP STANDARD I l (Indicate "S" 'for Sat. or "U" for Unsat.) ("C" denotes critical step) , l I START TIME: ;
- 1. Locate correct procedure. 1. Obtains EPP/IP 5.3.
Comments: NOTE: Steps 2 through 8 follow , 1 flow path of Att. 1. The (O information can be obtained from other locations in the I procedure. .
- 2. Verify that there is a 2. Identifies that an Alert declared emergency. has been declared.
1 l Comments.: l l l l EVALUATOR CUE: An Alert was given in the initial conditions. l i
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Page lof 4 Revision 0
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,W. RTL #A5.635.J l O \
- .Q I NUMBER TITLE l ADM-Emer Ex Determine Emergency Exposure Limit 1
i i STEP STANDARD (Indici.te "S" for Sat. or "U" ("C" denotes critical step) for Unsat.) ,
- 3. Verifies individual is 3.1 Verifies with Health _
qualified as radiation Physics that the individual J worker, and are not declared are radiation workers. i 1 pregnant. 3.2 Verifies that ANSS is NOT l declared pregnant. Cramments: 4 i
^
EVALUATOR CUE: The necessary information was given in the ' initial conditions. ,
- 4. Identify that the exposure 4. Verifies the exposure is is necessary to Save a human necessary'to Save a human life. life.
Comments: EVALUATOR CUE: Initial Conditions indicated this need. T R Page 2of 4 Revision 0
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'RTL #AS.635.J i.
,n NUMBER TITLE ADM-Emer Ex' Determine Emergency Exposure Limit STEP STANDARD (Indicate "S" for Sat. or "U"
("C" denotes critical step) for Unsat.)
- 5. Determine if the individual 5.1 Verifies the individua'l is is a volunteer, a volunteer.
Comments: EVALUATOR CUE: This information was given in'the initial conditions. ,]
. sg EVALUATOR CUE: If asked, provide cue that the ANSS has no previous -
emergency exposures.
- 6. Determine'if the Unit 1 ANSS 6. Verify that the Unit 1 ANSS has.been briefed. has been briefed.
! Comments: I EVALUATOR CUE: This information was given in the initial conditions. l l I 1 Page 3of 4 Revision 0
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.g 1 i RTL,#AS.635.J
;f %
jV NUMBER TITLE
.~ADM-Emer Ex Determine Emergency Exposure Limit l
i I 4 STEP STANDARD (Indicate "S" for Sat. or "U" . ("C" denotes critical step) for Unsat.) .
- 7. Determines that the DLC 7. Verifies that the DLC chief chief Nuclear officer has Nuclear officer has not not authorized exposures authorized exposures > 75
.>75' Rem. Rem.
1 l l I EVALUATOR CUE:-This information-was given in the initial conditions. j y
- r 8.C Determine the allowable 8.C Determines that the dose. allowable dose will be 75 Rem TEDE, 225 Rem lens.of eye and 750 Rem organ CDE. .
Comments: STOP TIME l u) . ? . L i- ! Page 4of 4 Revision 0 l' _ . _
d' RTL #AS.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE CANDIDATE DIRECTION SHEET '\-) !
- THIS SHEET TO BE GIVEN TO CANDIDATE
- Read:
Determine the maximum allowable limits for emergency Taska exposure. INITIAL An Alert has been declared at Unit 2 due to LOCA. An pera r as slipped an fallen in the VCT cubicle CONDITIONS,
- while troubleshooting erratic VCT leveJ. indications.
The operator is bleeding profusely, from the scalp. Health Physics has determined extremely high radiation exists in the VCT cubicle. The emergency squad believes the individual will bleed to death if he doesn' t receive prompt medical attention. The Unit 1 ANSS has volunteered to enter the VCT cubicle to extract the victim. His Rad worker qualifications are I current for BVPS and Rad con supervision has briefed him on the risks associated with his projected dose for the extraction of the operator from the VCT
/~T cubicle. Jim Cross (Duquesne Light Chief Nuclear
(. ) Officer) has been briefed of the situation and has NOT, and WILL NOT authorize additional exposures.. You are the Emergency Director. Determine the emergency exposure limitation for the Unit 1 ANSS to perform this extraction. 1 i At this time, ask the evaluator any questions you have on this JPM. l When satisfied that you understand the assigned task, announce l "I am now begir<ning the JPM" . l Simulate performance or perform as directed the required task. ! Point to any indicator or component you verify or check and I announce your observations. After determining the Task has been met, announce "I have completed the JPM". Then hand back this sheet to the evaluator. O
,v l
l
BEAVER VALLEY JOB PERFORMANCE MEASURE EVALUATOR COVER SHEET JPM Number: ADM-PAR Rev: O System #: 2.4 Faulted: JPM
Title:
Determine PAR K/A
Reference:
2.4.44 / 4.4 Task ID #:3440240302 JPM Designation: O NO O RO x SRO JPM Application: X NRC X Initial Exam O Training Evaluation Method LOCATION TYPE X Perform Plant Site Training Simulate Simulator O Annual Requal. Exam
@ Classroom O OJT E Initial'Op'rator e Exam Administered By: Other:
O Bv-T NRC 0 other: Evaluation Results Performer: Name: Employee No: Results O SAT Time (minutes) UNSAT* Allotted: 15 Actual: Time Critical: Yes @ No
- Comments (Required for UNSAT Evaluation):
l l Evaluation Results O Check here if same as above l Observer 1: Name: Employee No: l Observer 2: Name Employee No: Observer 3: Name Employee.No: Observer 4: Name Employee No: Time (minutes) Results Question ID Allotted Actual SAT UNSAT* Question #1 O Employee No: Question #1 O O Employee No:
- Comments (Required for UNSAT Evaluation):
l O Evaluator (Print): Organization: l Evaluator Signature Date:
w R1L #AS.635.J . BEAVER VALLEY JOB PERFORMANCE MEASURE
/~'s EVALUATOR DIRECTION SHEET
.i JPM NUMBER: ADM-PAR JPM TITLE: Determine PAR TASK STAN.: Protective Action Recommendations determined in accordance with EPP/IP 4.1 RECOMMENDED STARTING LOCATION: CONTROL ROOM DIRECTIONS: You are to simulate (perform) the task Determine PAR. INIT. CONDITIONS: 25 minutes ago a LOCA occurred with a I.oss of Both AE and DF busses. Power to the Busses has NOT been restored. The following plant conditions exist: o 8 hottest Core Exit TCs indicate 7492F. o Subcooling is -162 F.
\- o RVLIS Full Range indicates 35%.
(No RCPs running) o 150' wind direction is from 120* at 15 MPH. - o 500' wind direction is from 128* at 19 MPH. O Dose projections are not yet a,vailable, and are expected in about 30 minutes. INIT. CUs: You are the Emergency Director and the TSC/ EOF have not yet been activated. You are to evaluate the above conditions and determine which, if any, Offsite Protective Action Recommendations are necessary.
REFERENCES:
EPP/IP 4.1 Rev. 9 TOOLS: NONE HANDOUT: NONE (EPP and EPP/IPs are.to be made available to candidate.) f'\ b
s: 1
=RTL #A5.635.J NUMBER TITLE
(- ' ADM-PAR' Determine PAR
+
STEP STANDARD ' (Indicate "S".for Sat, or "U" ("C" denotes critical step) for Unsat.) _ START' TIME: EVALUATOR NOTE:'The, candidate ! may begin by determining Critical Safety Function status or by evaluating event classification prior to referencing EPP/IP 4.1
-f
() 1. Review EPP/IP 4.1. 1.1 Candidate locates EPP/IP 4.1.- ; 1.2 Candidate determines that Protective- - Action Recommendations required within 15 minutes if General Emergency is declared. COMMENTS: I i Page 1 of 4 Revision 0
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V RTL #AS.635.J . r . NUMBER TITLE ADM-PAR Determine PAR STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.)
- 2. Candidate determines 2.1 Candidate determines a General Emergency General Emergency condition exists. using EPP IPs.
EVALUATOR NOTE: TAB 3.1 is expected classification. Others may also apply. EVALUATOR NOTE: Candidate may f ,r T reference EOPs to determine ' !, j)
~
that CSF Red Path conditions exist. COMMENTS:
- 3. Candidate refers to 3.1 Candidate enters e Offsite Protection Offsite Protective Action Recommendation Action l' Flow Chart. Recommendation Flowchart on General Emergency EAL other than 7.1.
l COMMENTS: 4 /~%
\.s) l Page 2 of 4 Revision 0 l-
RTL #A5.635.J NUMBER TITLE ADM-PAR Determine PAR STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.)
- 4. Reference Attachment 2 4.1 Candidate references and Determine Downwind Table 1 to determine Wedge. that the 150' elevation Downwind Sectors are MNPQR.
4.2 Candidate references Table 1 to determine that the 500' elevation Downwind l/} (s ,/ Sectors are NPQRA. i COMMENTS: 5.C Determine Offsite 5.1.C Candidate. determines the Protective Action following Protective Recommendation. Action Recommendation: Evacuate 360 for two miles. Evacuate Sectors < l MNPQRA for five miles. Shelter remainder of 10 mile EPZ. 4
- COMMENTS:
l l Page 3 of 4 , Revision 0 i
4 a RTL #A5.635.J 1
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TITLE (_\) NUMBER ADM-PAR Determine PAR l l l l' STEP S".ANDARD (Indicate "S" for Sat. or "U" l i ("C" denotes critical step) for Unsat.) l l . I Report JPM completion. 6.1 Candidate reports 6. that the JPM is complete. COMMENTS: l l 'O STOP TIME l-t l I G- ., V r . Page 4 of 4 Revision 0
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r RTL #AS.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE i rx CANDIDATE DIRECTION SHEET
, s
- THIS SHEET TO BE GIVEN TO CANDIDATE Read:
Task: lDeterminePAR 25 minutes ago a LOCA occurred with a Loss of INITIAL Both AE and DF busses. Power to the Busses has CONDITIONS: NOT been restored. The following plant conditions exist: o 8 hottes't Core Exit TCs indicate 749 F. i o Subcooling is -162 F. I o RVLIS Full Range indicates 35%. (No RCPs running) o 150' wind direction is from 120* at 15 MPH. o 500' wind direction is from 128' at 19 MPH. o Dose projections are not yet available, and are expected in about 30 minutes.
,m \
INIT. CUE: lYouaretheEmergencyDirectorandtheTSC/ EOF have not yet been activated. You are to evaluate the above conditions and determine which, if any, Offsite Protective Action Recommendations are l necessary. At this time, ask the evaluator any questions you have on this JPM.
~-
When satisfied that you understand the assigned task, announce "I am now beginning the JPM". Simulate performance or perform as directed the required task. Point to any indicator or component you verify or check and announce your observations. After determining the Task has been met, announce "I have completed the JPM". Then hand back this sheet t'o the evaluator. A r b
%)
l, Appendix D Scenario Outline Form ES-D-1 ( Facility: .3.e. aver Vallev Power Station Unit 2 Scenario No.: 1 Op-Test No.: 2 LOT 2A l l Examiners: Operators: Objectives: To evaluate the aoolicants ability to use Normal. Abnormal. Emeroenev. and Alarm Resoonse orocedures to reduce reactor oower. olace the Condenser FW1Qumo system in service and respond to the failure of the steam oressure inout. to resoond to a diocoed control bank rou w . M to a steam leak. to recoanize the failure of the Source Ranae i delectors to automatically eneraize: to recoanize and take manual actions to resoond to a failure of automatic reactor trio l and safety iniection: and to use procedures to respond to a steam aenerator tube ruoture coincident with a steam leak. Initial Condtions: The olant is at 20% oower havina reduced from 50% a<miilibrium condtions. The olan is to reduce to 15%: power. Rods pre in Manual. The Startuo Feedwater Pumo is 00S. as is one Motor Driven AFW oumo. Tumover The crew is to take the Unit off-line in accordance with 20M.52.4.C and olace the plant in a stable Mode 3 condtion. (2FWS-P24) and [2FWEYLBi c a 00S. Event No. Malf. No. Event Event Type' Description 1 N/A R-RO Reduce Power to take Unit off-line N-PO I N-SRO I 2 CLF. 2 MSS-PT464 failure high after Steam Dumps placed in Steam Pressure Mode RO/ POI l(. MSS 44 SRO 3 MAL C Dropped Rod (G7); RO must pull rods to stabilize. Tech Spec entry. CRF3 RO/SRO l l 4 MAL M MSIVroom steam leak with temperature rising, even!vally requiring reactor l MSS 2A RO/P0/ Iny - SRO 5 CLF/BST I Source range detector fails to automatically energize; RO must manually NIS7 ROISRO energize l 6 MAL C Failure of Auto Reactor Trip PPL1A, RO/SRO 1B 7 MAL C Auto Failure of Safetyinjection l PPLSA, P0/SRO I l SB 8 MAL MT Steam Generator Tube Rupture in 'C' S/G RCS4A RO/P0/ SRO
* (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
' Interim Rev. 8, January 1997 NUREG-1021 1 of 2 4
L lQ 13 Scenario #1 summary description. l Unit 2 is at 20% power reducing load to remove the unit for maintenance activities. After receiving the turnover, the crew will reduce Turbine load to place i the Steam Dump System into service in the Steam Pressure mode in accordance with the Normal Operating Procedures. Once Steam Dumps are placed in auto, there will be a failure of the pressure transmitter feeding the controller (2 MSS-PT464). This will cause the Steam Dumps to open and require manual action by the PO to prevent an uncontrolled cooldown of the primary plant. Prior to this, a failure will be placed in the Rod Control system such that if the RO moves rods, Control Rod G7 will fallinto the core. This is a Tech Spec entry and will require the use of the Abnormal Operating Procedures. As crew is responding to the dropped rod, there willbe a steam break in the Main Steam Valve Room. There will also be indications of high Main Steam Valve Room temperatures, indicative of a steam leak. This leak will continue to worsen, resulting in a reactor trip and safety injection, which are both blocked from automatically actuating. The crew must manually initiate them. Post trip will result in a Steam Generator Tube Rupture. Also, the Source Range Detectors will not automatically energize, and must be manually energized. The scenario will continue until the crew stabilizes the plant in ECA-3.1, SGTR with Loss of Reactor Coolant. I'*h V kJ 2 of 2
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b Beaver Valley Power Station Unit 1/2 1/2O M 4 .1.C CONDUCT OF NERATIONS Issue 4 Revision 3 'p ORGANIZATIONAL AND RESPONSIBILmES OF THE OPERATIONS GROUP Page C 7 of 28 d SHIFT TURNOVER AND RELIEF - l Figure 48.1.C-2, Assistant Nuclear Shift Supervisor Shift Turnover Checklist Record type A9.3411 . Assistant Nuclear SNft Susennsor .BVPS Un64 Me. SHIFT TURNOVER CHECKLIST esee tsee 2deo
- 1. Oncoming and offgoing MISS conduct a few6ew of the centret boards ettseruing eve 4utions in progress, O O O unusual equipment or systems status and any unusual alarms or inecations or status lights.
. 2. Reuew previous shaft narratsve legs, (oncoming) O O O
- 3. Discuss ~ any identified trends that require special attention. O O O
- 4. Ol* cuss any temporary legs, parameter troneng or temporary procedures in effect. 0 0 0'
- 5. Review MSPs, OSTs, BVis, PMPs (or other precedures affecting control room indicahons)in progress or 0 0 0 scheduled (oncoming).
- 4. Discuss any gas or liquid discharges in progress. O O O
- 7. Ust on reverse any Tedinical Specificamen items in effect (ty offgesng). Rew6ew list (oncoming). O O O p 8. Vertfy normal shift complement and emergency squad requirements are met (oncoming). O O O
- 9. Rewtow the Oearence Program for posted and signed en clearances. 0 0 0
- 10. Rewtow the current Equipment OOS computer tracidag seg prtateut (encoming). O O O 11, Review the ESF Mimic Print for out of mennel condialens knoorring). O O '
Discuss status of procedures in progress, being turned ewe *. O O O
- a. Circle the priority train 14 N/A for att meres other than A or 8 A or B A or 8 Modes 5 and 6
- b. Verify Normal and emergency power le pr6ertty train .N/A for all modes other than N E NE NE Modes 5 and g o0 00 00 l 14. The Nuclear Control Operators narrstrwe log; S1-4,5,8; er the NOMS Narrative log (dependent on which 0 0 0
( is in use), has been rewtowed to assure att significant items have been insted with adequate description.
- 15. Oncoming ANSS, log five ($) qualified fire brigade members in the ANSS tog; S-16,17,18,if in use. 0 0 0
- 14. The offgoing ANSS signature certifies that their narrative tog entries and the tour log entries made on 0 0 0 their shift arie accurate, clear, concise and complete and that they f: ave been property rel6eved.
- 17. The offgoing ANSS prints out current copies of the Equipment OOS computer traciong log and distributes 0 0 0 to each watch station.
(Offgoing) (Oncoming) l l
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(Signature) . Date/ Time (Signature) Date/ Time I (Signature) Date/ Time (Signature) . Date/ Time (Signature) Date/ Time (Signature) Date/ Time I
- 18. The oncoming ANSS has reviewed the approved Control Room copy of the OST sched.Ae.
(Unit 2 LER 9H03) (Signature) (Signature) (Signature) 1 a' f l{ (Example . FRONT)
- b i
l FOR TRA'NING USE ONLY \
. . - . - . . . -- - - . . - - - ~ . . . ~
Beaver Valley Power Station Unit 1/2 1/20M-48.1.C l CONDUCT OF OPERATIONS Issue 4 Revision 3 [N ORGANIZATIONAL AND RESPONSIBILITIES OF THE OPS. GROUP Page C8 OF 30
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\h-SHIFTTURNOVER AND RELIEF TECH SPEC ACTION ITEMS IN EFFECT (Soccial Surveillence Below) ;
l Component / T. S. No. Date/fime Date/ Time Date/ Time I System Applied Due Complete !
- 1) 2FWE*P23B 3.7.1.2.c Today -6 hrs ago 66 hours from now
- 2) 2FWS-P24 INFO l
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1 1 f. s REMARKS: 00-08 iI 1. Pump bearing replacement in progress. 2FWE*P22 aligned to 'B' header with 2FWE*36 (\# 2. shut and 2FWE*102 open. Info only - maintenance on speed increaser l REMARKS: 08-16 ; REMARKS: 16-24 (EXAMPLE) FIGURE NO. 48.1.C-2 Y ! Figure 48.1.C-2, Assistant Nuclear Shill Supervisor Tumover Checklist l' l l
' DUQUESNE'Llu OMPANY' ,;
Nuclear Power Division - Training' Administrative Manual ; 8-98-1 (iii)REV1 ' . INITIAL CONDITIONS IC 50 RCS boron - 373 PPM, CBD = 160 steps. Reactor power @ 20 % .. ADDITIONAL LINEUP CHANGES STICKERS VOND MARKINGS ~ ; 2FWS-P24 OOS - Pull-to-Lock Red DangerTag 2FWE*36 shut ; 2FWE*P23B OOS - Pull-to-Lock Red Danger Tag . 2FWE*102 open .[ 2FWS-MOV152 - De-energized Red Danger Tag 2FWE*38 shut .[ r Set up computer trend in accordance with 20M-52.4C r . step 8 ' EOUIPMENT STATUS DATE/ TIME T/S# AND TIME LIMIT MARK L 2FWE*P23B Today - 6 hours ago 3.7.1.2.c - 72 hour time limit [ 2FWE*P22 aligned to 'B' header j 1 INFO 2FWE*36 shut; 2FWE'102 open ! 2FWS-P24 SHIFT TURNOVER INFORMATION I
- 1. Crew is to reduce power in accordance with 20M-52.4C, beginning at step 13 A, page 11 of 28. Previous shift swapped feedwater to the bypass feed regulating valves and they are controlling in automatic. Steam Generator spare group is set up as per procedure (GPSPR 1). Operation with turbine load less than 90 Mwe for longer than 15 minutes is not expected. '
- 2. 2FWE*P23B OOS for pump bearing replacement. Expected to be returned in 18 hours. 2FWE*P22 aligned to 'B' header.
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- 3. 2FWS-P24 OOS for speed increaser maintenance.
j I 4. CCP System - LCV's controllers are disconnected on VB'C'. Valves are controlled in auto from the process racks. DCV's are in manual to reduce j
" hunting" and possible valves leakage.
SCENARIO SUPPORT MATERIAL - ; OM 1/2.48.1 Figure C-2 (ANSS Turnover Checklist) 20M-52.4C, Iss.1 Rev. 27, signed off to step 13. i Reactivity plan for shutdown. l
- INSTRUCTIONAL METHODS NOTES There shall be no direct intervention or assistance by the simulator instmctor. Terminate the drill when directed by the exam team. j I
DUQUESNE LI OMPANY . Nuclear Power Division Training Administrative Manual DRILL 8-98-1 REV 1 PAGE1 l PLANT STATUS OR RESPONSE l OBJECTIVE l EXPECTED STUDENT RESPONSE l l INSTRUCTIONAL GUIDELINES Initialize the simulator at IC-50 Reactor at 20% power having reduced from 50% equilibrium conditions. Boron is at 373 ppm and rods are at 160 on Bank D Crewis to decrease power using OM 52.4C , at step 13A. 1 Insert MAL PPL1A ACT,1,0,0,D Prevent Auto Reactor Trip MAL PPLIB ACT,1,0,0,D MAL PPL5A ACT,1,0,0,D Prevent Auto Safety Injection MAL PPL5B ACT,1,0,0,D BST NIS7 3,0,D Prevent NIS Source Range Detectors from automatically energizing Insert:
.............................. I VLV CRV271,0,D 2RVS-P24 recirc valve failure VLV CRV451,0,D 2FWS-MOV152 De-energized LOA IIIV71 1,0,D 2RVE-P23B OOS LOA AMV10,0,0,D 2RVE-P22 aligned to 'B' header t LOA ARV3 0,0,0,D 2RVE-36 shut; 2RVE-102 open LOA ARV131,0,0,D '
Aligns CCP system LCV's and DCV's to match plant configuration. FILE LRTM41C t
h L p DUQUESNE LIA,j0MPANY e~ (,s).. , Nuclear Power Division Training Administrative Manual DRILL 8-98-1 REV 1 PAGE2 INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l OBJECTIVE l EXPECTED STUDENT RESPONSE l l After PCS startup, insert . ANACK ANRSET FILE STUFFON FRZ Assign shift positions: NSS Simulator Frozen until after shift ANSS turnover unless it needs to be on RO momentarily for an alignment change. PO STA Conduct shift turnover with oncoming Oncoming operators should complete the required checidists and carry out a formal operators. shift turnover. When the shift turnover is complete, Simulator running. Crew assumes control of the unit. place the simulator to RUN and - commence the drill. , EVENT #1 - REACTOR POWER DECREASE T
p , . O DUQUESNELluL ZOMPANY . Nuclear Power Division Training Administrative Manual-DRILL 8-98-1 REV 1 PAGE3 INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l OBJECTIVE l EXPECTED STUDENT RESPONSE l l r Crew commences power decrease in accordance with reactivity plan. Continue reactor shutdown to 12 to Reactor at 20% power. , Procedure in effect is 20M-52.4C at step 15% power. 13 A on page 11 of 28 r IfTavg becomes less than 551F with Ann.' A4-3C "TAVG DEVIATION FROM TREF" ON, then-RO verifies Tavg > 541F RO initials with time and date on recorder 2RCS-TR410, wide range Tc Crew makes entry in NOMS stating Tavg will be verified > 541F once per 30 minutes while A4-3C is ON, and to initial, time , . and date 2RCS-TR410 every 30 minutes. RO/PO reduce turbine load to less than 15 % , i RO/PO verifies Ann. A12-3C, C5 Turbine load < 15% PERMISSIVE"is OFF PO verifies turbine drain valves open RO verifies rod controlin Manual
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DUQUESNELld bOMPANY , Nuclear Power Division Training Administrative Manual DRILL 8-98-1 REV 1 PAGE4 INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l OBJECTIVE l EXPECTED STUDENT RESPONSE l l
, Crew does not remove MSR's from service ,
at this time. PO verifies 2 MSS-FCV100E, F, A and C are open PO closes / verifies closed ' 2FWS-MOV154A, B, C L NSS/ANSS specifies load rate decrease Reactor Power at 12 - 15% RO lowers and stabilizes power at 12-15% ., RO maintains Tavg between 550F and } 553F When turbine load is < 10%, PO shuts down heater drain pumps 2HDH-P21 A,B , Turbine load less than 10% Turbineload stabilized Place Steam Dump System in Steam PO verifies Steam Dump Control Mode Pressure Mode Seldctor Switch isin Tavg mode , Pd verifies 2 MSS-PK464 Main Steam Manifold Pressure Controllerin AUTO i PO lowers Pressure controller setpoint - potentiometer until output meter rises , above zero ! l
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.b DUQUESNE lid.mf0MPANY / ,
Nuclear Power Division Training Administrative Manual DRILL 8-98-1 REV 1 PAGE5 INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l OBJECTIVE l EXPECTED STUDENT RESPONSE l l
- PO places PK464 in manual and verifies output is zero PO places Steam Dump Control Mode Selector Switch in Steam Pressure Mode PO places PK464 in Auto i
RO maintains TAVG 550 to 553F EVENT #2 2 MSS *PT464 Failure PO acknowledges ANN's and identifies ; After crew has placed the steam dump This will cause steam dump valves to system in the Steam Pressure Mode in open and require manual operator PT464 as the failed channe!. automatic, insert intervention.
****************************** PO reports diagnosis to ANSS XMT MSS 441,1200,120,0,D.
PO takes manual control of PK464 and closes steam dump valve ; RO controls Tavg , After crew stabilizes plant, control Rod RO verifies drop;ied rod and crew responds EVENT #3 G7 will drop into core. with appropriate ARPs. Dropped Control Rod' Insert:
....************************** ANSS transitions to AOP 2.1.8, Rod MAL CRF3A ACT,G7,1,0,0,D Inoperability Part A.
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DUQUESNE . Llw(D 2OMPANY b' ,
- Nuclear Power Division .
Training Administrative Manual DRILL 8-98-1 REV 1 'PAGE6 : EXPECTED STUDENT RESPONSE l .;
, l INSTRUCTIONAL GUIDELINES l- PLANT STATUS OR RESPONSE l OBJECTIVE l Rod at Bottom and Rod Deviation RO verifies only ONE rod dropped. ,
alarms. Tavg drops. Possible Tavg , deviation alarm RO places Rod Control to Manual RO checks Tavg greater than 541F and - within 4 degrees ofTref and stable ANSS declared the rod inoperable and 1 Power is less than 75% ! -shows intent to comply with TS 3.1.3.1.c.3 ! and verifies Shutdown Margin within one hour per TS 3.1.1.1 , ANSS notifies I&C and Reactor
- Engineering ,
ANSS notifies GMNO ofdropped rod ; As GMNO inform crew that since shutdown is in progress, recovery of 4 dropped rod is not required i RO/PO verify alarms EVENT #4 , Steam leak into the Main steam valve room. . Insert: Tavg Drops, Reactor Power increases MAL MSS 2A Main Steam Valve Area Temp High t ACT,3E+06,120,0,0,D alarm 4 6
..___m______.__._____..m_____.____..__m_.___ _ __.______...____--m__._._ __m._-__ _ _ _ _ - _ _ _ _ . _ _ _ _ . _ _ _ _ _ _ . _ _ _ _ _ _ _ - _ - _
b DUQUESNE Lluiv0'MPANY Nucle:r Power Division Training Administrative Manual - , DRILL 8-98-1 : REV 1 -PAGE7 ' INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l OBJECTIVE l EXPECTED STUDENT RESPONSE l l Crew may opt to manually trip the . Reactor Trip failure. First out RO manually trips Reactor , reactor before reaching the auto trip annunciator is Low Pressurizer setpoint Pressure. t Reactor trip, turbine trip, safety RO manually trips the reactor, informs i injection. ANSS of a reactor trip. j RCS pressure drops. First Out: Manual reactor trip or : PRZR pressure low reactor trip , t AS-4H, P0488D RO and PO commence immediate actions f Steps 1 - 7 of E-0 are immediate I ofE-0, ANSS references E-0 to verify actions. immediate actions. ! i Turbine trip due to reactor trip alarm RO verifies reactor trip. A5-6D lit. Rod bottom lights lit. Neutron flux dropping.
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RO sounds standby alarm, announces rea,ctor trip. NSS initiates EPP evaluation. It is not expected that the ANSS will '. classify the event at this time (3 man i crew)
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.(b) DUQUESNE LluLaOMPANY h (~T -
L/ .. Nuclear Power Division Training Administrative Manual DRILL 8-98-1 REV 1 PAGE8 OBJECTIVE l EXPECTED STUDENT RESPONSE l l INSTRUCTIONAL GUIDELINES l PLANT STATUS ORRESPONSE l Throttle or governor valves closed, PO verifies turbine trip. reheat stop orinterceptor valves closed. MSR steam supply block valve closed. PO ensures reheat steam isolation. Reheat controller reset pushbutton depressed. Main generator output breakers open. PO verifies generator trip. Exciter circuit breaker open. 2AE and 2DF busses energized PO verifies power to AC emergency busses. RO checks if Si is actuated, manually E-0 immediate actions complete. SI actuated. actuates both trains of SI. Note: Monitor crew performance if ES- " 0.1 is entered prior to SI actuation. PO verifies both EDG running. EDG #1 &2 running. I 2FWE*P23B OOS, P23 A running. PO verifies AFW status, notes TDAFW pump running, SOVs open. 2FWE*P23B OOS. 2FWE*HCV100A-F open.
T g * - DUQUESNE LIO COMPANY " Nuclear Power Division Training Administrative Manual .; DRILL 8-98-1 REV 1 - PAGE9 OBJECTIVE l EXPECTED STUDENT RESPONSE l l INSTRUCTIONAL GUIDELINES l PLANT STATd5 OR RESPONSE l RO verifies service water system in - > Service water pumps mnning. Service water header pressure 55 - 124 psig. service. HHSI pumps running. RO verifies SI status. HHSI flow indicated. LHSI pumps running.' l
.All valve indicating lights with red SIS i
marks lit. RO/PO verify CIA. j All indicating lights with orange CIA I marks lit. P RO/PO verify FWI , Alllights with green FWI marks lit. ! RO/PO check if main steam line isolation . CNMT pressure < 3 psig. required. ; Steamline pressure >. 500 psig. l Steamline pressure rate < 100 psig in 50 seconds. t RO checks CIB and CNMT spray status. . CIB alarm Al-2H not lit. CNMT ' pressure < 8 psig. PO establishes domestic water system i 2CCS-AOV118 open. ! One station air compressor mnning. cooling to the station air compressors. E
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I} DUQUESNE LItnJOMPANY (3 Q - Nuclear Power Division Training Administrative Manual DRILL 8-98-1 REV 1 PAGE 10 OBJECTIVE l EXPECTED STUDENT RESPONSE l l INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l RO/PO verify CCP in service. CCP pump mnning. RO verifies SR detector high voltcge Source Range Detectors Fail Ito _ SR channels aligned properly. switches in normal, transfers NR45 energize automatically (Preloaded) recorder to SR and IR displays. Can be manually energized. PO verifies AFW flow greater than 365 AFW greater than 365 gpm. gpm RO verifies RCS Tavg stable at or Tavg trending to 5470F. trending to 5470F. ANSS directs personnel to perform emergency safety function checklists. RO checks recirc spray pump status. Recirc spray pumps not running. PORVs closed (not leaking). RO dhecks PRZR isolated. Spray valves closed. Safeties closed (PSMS data). PRT conditions normal. PORV block MOVs energized and open. 0 . _ _ _ _ _ _ _._._.._.._.._.._.._.________________.________________________._..______._______.__________.________._.____m_..__.___.__________.____________..___________m
I s/ DUQUESNE LhgOMPANY - Nuclear Power Division Training Administrative Manual DRILL 8-98-1 REV 1 PAGE11 OBJECTIVE l EXPEC1ED STUDENT RESPONSE l l INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l RO checks if RCPs should be stopped. RCPs running. . RCS to SG XP < 145 psid. CCP flow normal. PO checks if any SGs are faulted.
'A' SG pressure dropping in an ,
uncontrolled manner. Determines ' A' is faulted l t ANSS directs transition to E-2, Faulted CRITICAL TASK: Crewisolates the SG Isolation, step 1 faulted SG and directs operator to close isolation valve (s) operated from outside PO manually actuates CREBAPS system the control room prior to transition out of E-2 Crew contacts Unit I to verify proper CREBAPS operation , RO/PO verify Main Steamline Isolation. Possibly previously verified in E-0 Indicating light with YELLOW marks lit. t If'A' SG is still blowing down, 'B' PO verifies 'B' and 'C' SGs not faulted and 'C' SG pressures will still be , dropping due to Tavg drop PO identifies 'A' SG as faulted , EVENT # 4 SGTR in 'C' steam generator Insert:
...e................e.........
MAL RCS4C ACT,650,0,0,D ' t RO verifies 2FWS-HYV157A closed l
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DUQUESNELIb2 JOMPANY Q - Nuclear Power Division Training Administrative Manual DRILL 8-98-1 REV 1 PAGE 12 OBJECTIVE l EXPECTED STUDENT RESPONSE l l INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l PO verifies 2FWS-FCV409 closed NOTE: If requested to go to the Main Steam Valve room for valve manipulations, inform crew that room can not be entered because ofsteam in room. Inform them that you will contact the control room whenever you are able to enter the room PO closes 2FWE*HCV100E & F PO verifies one motor driven AFW pump NOTE: Isolation of SG in E-2 and/or running and trips steam driven AFW pump E-3 can be assumed if 2FWE-P22 is tripped if AFW flow is isolated, and if 2SVS-HCV104 is closed. Manual valve manipulation is not required. ANSS directs an operator to close 2 MSS *15 steam supply to 2FWE*P22 ANSS directs an operator to reset the trip Command for closing 2 MSS *15: throttle valve on 2FWE*P22 once 2 MSS *15 is shut LOA AFW25 0,0,0,D
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RO/PO verifies 2SVS-HCV104 closed ANSS directs an operato'r to close 2SVS- i Command for closing 2SVS-27: 27 - steam supply to 2SVS-HCV104 , LOA MSS 9 0,0,0,D RO verifies 2BDG-AOV100Al closed RO closes 2SSR-AOV117A,B,C
DUQUESNELIGL LOMPANY Q Nucle:.r Power Division , Training Administrative Manual DRILL 8-98-I REV I PAGE 13 OBJECTIVE l EXPECTED STUDENT RESPONSE l [ ~ INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONZE l PO checks for ruptured SG , No level risingin an unexpected
. manner -
ANSS directs transition to E-1 Loss of NOTE: Crew may use re-diagnosis and Reactor or Secondary Coolant, step 1.
. transition directly to E-3 based on previous indications of tube leakage. If not Crew will transition to E-1 and then to E-3 PO checks CREBAPS actuated Previously done .
RO/PO check if RCPs should be stopped RCS to SG delta nressure less than . 145 psig with r. 3I flow indicated or t loss of CCP to RCP RO checks Recirc Spray Pump Status No pumps running. RO verifies CNMT Hydrogen Analyzers Analyzers mnning, amber light fit running PO checks for any new faulted SGs Previously done i PO checksintact SG levels NOTE: Crew may transition to E-3 at this point if SG levelis rising in an unc'ontrolled manner. RO checks PORVs and PORV Motor PORVs closed; Motor Operated Isolation valves open and energized Operated Isolation valves , PO closes 2FWS-FCV478, main feedwater i Isolate faulted SG
' to 'A' SG ,
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. . _ _ ___.________._._m._____ .___ ._.. _ _ __. _._____.________--._.m._____,______.__ .___m.___ ___.___ _ _ _ _ ______r -
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DUQUESNE LIGal COMPANY h-V Nuclear Power Division Training Administrative Manual
- DRILL 8-98-1 REV 1 PAGE14
.. l- INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l OBJECTIVE l EXPECTED STUDENT RESPONSE l-C SG level risi6g in an uncontrolled ANSS directs operator to check if SG manner. Secondary rad monitors not tubes are intact.
consistent with pre-event levels. 4 ANSS makes a transition to E-3 and informs crew. ANSS directs STA to monitor status trees. j i It is not expected that the ANSS will NSS declares an Alert due to SGTR that classify the event at this time (3 man results in an SI actuation or E-3 entry crew) (TAB 1.2.4 Loss indicator). Control room DRMS not in alarm, PO verifies control room habitability. CIB has not occurred. j RCPs running. RO checks if RCPs should be stopped. RCS to SG AP > 145 psid. CCP flow normal. . t
- 2CVS-P21 A,B PTL. . RO isolates CNMT vents and drains. -
2DAS-P204A,B stop. ' l 2DGS-P21 A,B, PTL, ; 4 [ Auto SI blocked A12-1C lit. RO resets SI(both trains). ! SI signal Al2-ID not lit. l I
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O - DUQUESNE LIddOMPANY a
~I Nuclear Power Division Training Administrative Manual 4 . DRILL 8-98-1 REV 1 -PAGE 15 #
OBJECTIVE - l EXPECTED STUDENT RESPONSE -l INSTRUCTIONAL GUIDELINES -l PLANT STATUS OR RESPONSE l l RO resets CIA and CIB (both trains). Both trains of CIA reset. CIB not actuated. -l Crew identifies ruptured SG. j C SG level rising in an uncontrolled
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manner. Secondary rad levels higher than normal. Crew isolates flow from ruptured SG.' s When ' A' SG blowdown complete, the _ Atmospheric steam dump valve actions for isolating ' A' and 'C' SGs 2SVS*PCV101C controller setpoint [ can be completed. adjusted to 100%, PCV closed.
-RO verifies 2SVS-HCV104 closed ;
RHR valve 2SVS*HCV104 closed. ; ANSS dispatches operator to isolate Insert the following to isolate the C SG 2 MSS-17 and 2SVS-29 from RHR valve and 2FWE*P22: l LOA MSS 110,0,0,D 2SVS*29 locally closed. " LOA AFW27 0,0,0,D 2 MSS *17 locally closed. , LOA AFW22 0,0,D Reset /open 2FWE*TTV22. ; l
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Report valve closures after an appropriate delay. i RO verifies 2BDG*AOV101Cl and !' CRITICAL TASK: Crew isolates feed Verify blowdown isolation valve , 2SDS*AOV111C1 closed flow into and steam flow from ruptured 2BDG*AOV100C1 closed. SG and directs operator to close Close main steamline drain valve isolation valve (s) operated from outside 2SDS* AOVillC1. j PO verifies 2SDS* AOV129A closed the control room before a transition to Close RHR piping drain valve ECA-3.1 occurs. 2SDS*AOV129A. l t i 9
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DUQUESNE Llu_JOMPANY - Nuclear Power Division Training Administrative Manual DRILL 8-98-1 REV 1 PAGE 16 OBJECTIVE l EXPECTED STUDENT RESPONSE l l INSTRUCTIONALGUIDELINES l PLANT STATUS OR RESPONSE l Close ruptured SG main steamline and PO closes 2 MSS *AOV101C and verifies . closed 2 MSS *AOV102C bypass valves 2 MSS
- AOV101C, 102C.
PO checks mptured SG level.- C SG narrow range level greater than . 5%. Feedwaterisolation (green FWI marks) previously verified. 2FWE*HCV100A,B closed. RO checks PRZR PORVs block valves, Power to block valves available.
. PORVs closed (not leaking). and safeties.
Safety valves closed (PSMS data). PO checks if any SGs are faalted. No new SG pressure droppingin an uncontrolled manner. No SG completely depressurized. Narrow range level greater than 5%. PO checks intact SG level. Control feed flow to maintain SG narrow range levelbetween 5% and 50%.
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PO verifies mptured SG pressure greater - 3 Crew may transition to ECA-3.1 here if SG pressure >i65 psig. than 265 psig. ruptured SG pressure is less than 265 Psig ANS determines target temperature for Based on ruptured SG pressure. cooldown. 4
- - - _ . . - . - - _ . - _ _ . . _ _ _ _ . - - - _ _ - - . _ _ _ . - . _ _ _ - _ - . - - - - - . - - - - - _ - - - - -- . . , . - - - , . . - , - .,--. , ~ . . - - -
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'DUQUESNE LIGaiCOMPANY (V.) .
Nuclear Power Division ' , Training Administrative Manual DRILL'8-98-1 REV 1 - PAGE 17- ,
-l- INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE - l- OBJECTIVE l EXPECTED STUDENT RESPONSE l'
. t Crew trends cooldown every ten minutes on main computer.
i Steam dump is available, greater than PO selects steam dump to steam pressure mode and dumps steam at maximum rate. : 100 F per hour cooldown. RO blocks low steamline pressure SI when PRZR pressure is less than 1950 psig. . i STA monitors thermocouples. 4 i Condenser steam dump controllerin PO stops cooldown when core exit \ auto with pot setting corresponding to TCs < target temperature. current intact SG pressure. PO checks ruptured SG pressure. Crew may transition to ECA-3.1 here if Pressure stable. . ruptured SG pressure is less than 250 i psi above intact SG Crew checks on RCS subcooling. Crew may transition to ECA-3.1 here if Subcooling > 61 F. subcooling does not me'et requirements 21 A and C RCPs not running, spray RO depressurizes RCS to minimize break . valves not available. flow and refill PRZR. i
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O- n DUQUESNE LlwdOMPANY Nucle r Power Division-Training Administrative Manual DRILL 8-98-1 REV 1 ' PAGE 18 - OBJECTIVE l EXPECTED STUDENT RESPONSE l INSTRUCTIONAL GUIDELINES -l PLANT STATUS OR RESPONSE- - l ~l RO depressurizes RCS using PORV -- NOTE: Przr level may be > 76% prior to reaching the depressurization steps. If this is the case, crew will move ahead to establishing charging and letdown. RO closes PORVs when conditions are PRZRlevel > 76%, or subcooling less than Attachment A-5.1, or RCS m et. pressure < mptured SG pressure and PRZR level > 4%. RO checks RCS pressure stable or rising Subcooling > 41F or attachment 5.1 Crew checksif SI can be terminated Secondary Heat Sink RCS pressure stable or rising Pressurizer level > 4% RO stops one Charging /HHSI pump PO checks one Station Air Compressor Previously done mnning RO establishes Normal Charging Close FCV122 , Open MOV310 and 289
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Control FCV122 to maintain level ' RO closes 2 SIS-MOV867A,B,C,D RO control charging to maintain PRZR level 14 -50% RO verifies SI not required Subcooling >41F or attachment 5.1 PRZR Level > 4% 9 e
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V .. DUQUESNELE 4 COMPANY U.-
' Nuclear Power Dmsson Training Administrative Manual -i l
DRH18-98-1 REV 1 PAGE 19 ~
- l ' EXPEC1ED STUDENT RESPONSE l t OBJECTIVE
_l INSTRUc110NAL GUIDELINES l PLANT STATUS ORRESPONSE l i RO checks if CNMT spray should be Spray not in service stopped PO establishes instrument air to . j Previously done ! containment 1 Crew establishes Letdown flow Pressurizer level > 14% - CCP in service s Monitor letdown rad monitor :, Adjust FC.V122 to 30-50 gpm ' Open AOV204 Place PCV145 to manual and 50% Open 460A & B j Open 200A, B, and/or C Place PCV145 in auto [ Open CCP valves to Aux Bldg ANSS transitions to ECA-3.1
' The followingis forif the crew !
transitions to ECA-3.1 i Crew checks RWST level > 460" j Transfer to recirc setpoint (not ! expected) .; PO establishes domestic water cooling to Previously done station air compressors - ; t PO checks one Station Air Compressor Previously done running
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l _ . . . _ _ _ _ _ _ _ _ . _ _ . . . _ _ _ . _ _ _ _ _ _ _ _ _ _ . - _ _ _ - _ _ _ _ _ _ _ . __----_s - - _ _ _ _ _ - .*e- a_ _ _ - _ _ _ _ _ ~ - e --- A*+' +*-e- --+m
DUQUESNE Liu OMPANY Nuclear Power Division Training Administrative Manual DRILL 8-98-1 REV 1 PAGE 20 OBJECTIVE l EXPECTED STUDENT RESPONSE l l INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l Open 2IAC-MOV131 and MOV130 PO establishes Instnament Air to Check air pressure > 85 psig Containment PO verifies all 4kv buses energized from off All buses energized from offsite site power RO checks if CNMT spray should be No spray pumps running stopped PO checks ruptured SG level Level > 5% and isolated PO checks if LHSI pumps should be RCS pressure > 185 psig and stable or stopped rising ANSS initiates evaluation of plant status Aux building and Safeguards radiation levels PASS system samples Plant alignment PO checks for any faulted SG Pressures dropping in an uncontrolled manner or completely depressurized
' (Previously done)
PO checks intact SG levels
~ Intact SG levels 5 - 50% (33% adverse)
Trend coH ieg temperatures Crew initiates RCS cooldown to Cold CRITICAL TASK: Crewinitiates Shutdown cooldown to cold shutdown at Block Low Steam Line Pressure SI at maximum achievable rate but less than <1950 psig 100F/hr in all RCS cold legs. Dump steam
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Nuclear Power Division Training Administrative Manual DRILL 8-98-1 REV 1 - PAGE 21 OBJECTIVE l EXPECTED STUDENT RESPONSE l l INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l Terminate drill whenletdown i estrblished and PRZR levelis droppingin E-3 or when cooldown is commenced in ECA-3.L : Operator logs should be clear, accurate and { Collect and review logs aner allowing concise. operators to complete them. Erase any VOND markings associated ! with this drill. NOTE: The expected EPP declaration is an ALERT on Tab 1.2.3 or 2.3 (If crew recognized auto rx trip failure) I l i
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,m Appendix D beer,ario 0utline Form ES D-1
'! (%/) Facility: Beaver Vallev Power Station Unit 2 Scenario No : _? Op Test No.: 2 LOT 2A Examiners: Operators: Objectives: To evaluate the aoolicants ability to use Normal. Abnormal. Emeraencv. and Alarm Resoonse crocedures to raise reactor oower. resoond to feed flow oroblems. oressurizer oressure control oroblems. VCT level control system oroblems. loss of oHsite i oower and Emeroency 91~el Generator orablems. auxiliary feedwater oroblems. ESF eauioment problems. and a smallbreaklQQA initial Conditions: The olant is at 48% oower and has been released to ao to 100% oower in accordance with 20M-52.48. Rods are in Manual TumoverRetum the olant startuo to 100% oower. [2FWS-P241 andj2FWE*P2381 are OOS. Event No. Ma:f. No. Event Event Type
- Description i N/A R/R0 Powerincrease.
N/P0/ SRO 2 CLF. XMT I Failure of Steam Pressure Compensation Channel for Feed Flow / Steam Flow. MSSSO P0/SRO TS entry , rh 3 CLF WT # Dg 30/SRO 4 CLF-XMT I 2RCS*PT444 fails high RCS28 RO/SRO 5 CLF-CNH C PORV sticks open; block valve will dose, but leaking; will eventually require RCS3 RO/SRO reactor ' rip. 6 MAL M Loss of offsite power on auto bus transfer, #2 EDG auto starts; #1 EDG will not OGS/A R0/PO start manually or automatically SRO 7 M Terry turbine trips, no longer delivers any flow requiring entry into FR-H.1 SRO 8 Auto C Containment isolation valves for Containment Instrument Air fail to close fai/ure P0/SRO automatically. Valves will close in manual.
* (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor t n i V)
( NUf4EG-1021 1 of 2 Interim Rev. 8, January 1997 l
l L/ Scenario #2 summary description. Unit 2 is at 48% power with a planned increase to 100% using Normal Operating Procedures. After power has been raised > 5% power, the Steam Pressure compensation input into the Steam Generator Water Level Control system will fail, requiring manual operator action to prevent a trip. Next VCT level Transmitter 2CHS-LT112 will fail high, requiring operator action to stabilize the CVCS system. j Next, 2RCS*PT444 will fail high, resulting in a PORV and two' spray valves failing ' open. When the operator manually restores pressure control, the PORV will stick open, requirin0 the manual block valve to be closed. The block valve will not completely close, and pressure will continue to drop. This will require the crew to make a decision on whether to shut down or trip the reactor. Either way, a loss of off-site power will occur at the time of the trip. Emergency Diesel Generator 2-1 will fail to start in auto or manual, and 2 2 will auto start. Three Containment Phase A valves will fail to automatically close requiring the operator to manually l close them. The steam driven Auxiliary Feedwater pump (the only source of l secondary feed) will be tripped, resulting in a total loss of Feedwater, and l transition to FR-H.1, Loss of Secondary Heat Sink. The scenario will be terminated l once a source of feedwater is established, and the crew secures one HHSIpump in ES-1.1, Si Termination. m >k e I 2 of 2 l l
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- Beaver Valley Power Station Unit 1/2 1/2OM48.1.C l CONDUCT OF OPER ATIONS lssue 4 Revision 3 ,G ORGANIZATIONAL AND RESPONSIBILITIES OF THE OPERATIONS GROUP Page C 7 of 28
. t 4 i V SHIFT TURNOVER AND RELIEF - i l Figure 48.1.C-2, A'ssistant Nuclear Shift Supervisor Shift Turnover Checklist i Record type 1 49.34ti - Asssstant Nuclear Shift Superwsor ,0VPS (Jnit No. SHIFT TURNOVER CHECKLIST 0000 1844 2400
- 1. Oncoming and offgoing ANSS conduct a towaw of the centrol boards observing evolutions in progress. O O O unusual equipment or systems status and any unusual alarms or Indications or status lights.
- 2. Review previous shift narratsve logs. (oncoming) O O O
- 3. Discuss any identified trends that require spedal attenuen. O O O
- 4. Discuss any temporary logs, parameter trending of temporary procedures in effect O O O
- 5. Review MSPs, OSTs. BVTs, PMPs (or other procedures affectang control room Indications)in progress or O O O scheduled (oncoming).
- 6. Discuss any gas or 16 quid discharges in progress. O O O
- 7. Ust on reverse any Technical Spedfication Mems in effect (by offgoing). Review list (oncommg). O O O
- 8. Verify normal shift complement and emergency squad requirements are met (oncoming 1 O O O
- 9. Review the Qaarance Program for posted and signed on clearances. O O O
- 10. Rwlew the current Equipment OOS computer traciong tog printout (oncoming). O O O
- 11. Review the ESF Mimic Print for out of normal condstons (oncerning). O O O f\ 12. Discuss status of procedures in progress, being turned over. O O O U -
- a. Circle the priority traint8 N/A for all modes other than A or B A or B A or B Modes 5 and 6
- b. Verify Normal and emergency power to priority train N/A for all modes other than H E NE NE ~~
Modes 5 and 6 00 0 0 0 0 14, The Nudear Control Operators narrative log; S1-4, 5, G; or the NOMS Narrative log (dependent on which O O O is in use), has been rev6ewed to assure all significant items have been listed with adequate description.
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- 15. Oncoming ANSS, tog five (5) qualified fire brigade members in the ANSS log; S 16,17,18 If in use. O O O
- 16. The offgoing A'NSS signature certafles that theer narrative log entries and the tour log entries made on O O O their shift arit accurate, clear, condse and complete and that they have been property relieved.
t 7. The offgoing ANSS prints cut current copies of the Equipment OOS computer traciong tog and distributes O O O to each waten station.
. (Offgoing) (Oncoming)
(Signature) Date/ Time (Signature) Date/Yime (Signature) Date/ Time (Signature) . Mte/ Time (Signature) Date/ Time (Signat <e) Date/ Time 1 ! 18. The oncoming ANSS has reviewed the approved Control Room copy of the OST schedule. (Unit 2 LIR 9H03) (Signature) (Signature) (signature) (C.xample . FRONT) G l FOR TRAINING USE OEY
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! Beaver Valley Power Station Unit 1/2 1/20M-48.1.C
- l. CONDUCT OF OPERATIONS Issue 4 Revision 3
[ ORG ANIZATION AL AND RESPONSIBILITIES OF Tile OPS. GROUP Page C8 OF 30 SiliFTTURNOVER AND RELIEF TECH SPEC ACTION ITEMS IN EFFECT(Soccial Surveillence Below) Component / T. S. No. Daterrime Date/ Time DateHime System Applied Due Complete
- 1) 2FWE*P23B 3.7.1.2.c Today -6 hrs ago 66 hours from now
- 2) 2FWS-P24 INFO REMARKS: 00-08 l (~. 1. Pump bearing replacement in progress. 2FWE*P22 aligned to 'B' header with 2FWE*36
.t ( '~ shut and 2FWE*102 open.
- 2. Info only - maintenance on speed increaser I
REMARKS: 08-16 REMARKS: 16-24 l l (EXAMPLE) m FIGURE NO. 48.1.C-2 i! )I N. I - l Figure 48.1.C-2, Assistant Nuclear Shift Supervisor Tumover Checklist
DUQUESNE L1 OMPANY - Nuclear Power Division Training AdministrativeManual 8-98-2 (iii)REV1
. INITIALCONDITIONSIC 42 RCS boron - 870 PPM, CBD = 171 steps. ' Reactor power @ 48 %. . ADDITIONAL LINEUP CHANGES STICKERS VOND MARKINGS 2FWS-P24 OOS - Pull-to-Lock Red Danger Tag 2FWE*36 shut
- 2FWE*P23B OOS - Pull-to-Lock Red Danger Tag 2FWE*102 open.
2FWS-MOV152 - De-energized Red Danger Tag 2FWE*38 shut EOUIPMENT STATUS DATE/TIMi T/S# AND TIME LIMIT MARK 2FWE*P23B Today - 6 hours ago 3.7.1.2.c - 72 hour time limit 2FWE*P22 aligned to 'B' header 2FWS-P24 INFO 2FWE*36 shut; 2FWE*102 open SHIFT TURNOVER INFORMATION
- 1. Crew is to raise power in accordance with 2OM-52.4B, Part A. The previous shift has completed QPTR 2OST-2.4.A sat.
- 2. 2FWE*P23B OOS for pump bearing replacement. Expected to be returned in 18 hours. 2FWE*P22 aligned to 'B' header.
- 3. 2FWS-P24 OOS for speed increaser maintenance.
- 4. CCP System - LCV's controllers are disconnected on VB'C'. Valves are controlled in auto from the process racks. DCV's are in manual to reduce
" hunting" and possible valves leakage.
SCENARIO SUPPORT MATERIAL OM 1/2.48.1 Figure C-2 (ANSS Turnover Checklist) 20M-52.4B, Iss.1 Rev. 30, signed off to step 2 Reactivity plan for startup. - INSTRUCTIONAL METHODS NOTES There shall be no direct intervention or assistance by the simulator instructor. Terminate the du.. when directed by the exam team. 4 4
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. Nuclex Power Division i Training Administrative Manual DRILL 8-98-2 REV 1 PAGEl' OBJECTIVE l EXPECTED STUDENT RESPONSE l INSTRUCTIONAL GUIDELINES -l PLANT STATL 3 OR RESPONSE l l
Reactor at 48*/o power, 870 ppm, XE Initialize the simulator at IC- 42 stable . Bank D at 171 steps. In 20M-52.4B, Part B, at step 2 QPTR 20ST-2.4.A completed sat All necessary notifications have been made and permission to increase load has been received. Insert: esee............................ VLV CRV271,0,D 2RVS-P24 recirc valve failure VLV CRV451,0,D 2FWS-MOV152 de-energized LOA HIV711,0,D 2RVE-P23B OOS LOA ARV10,0,0,D 2RVEP22 aligned to 'B' header LOA ARV3 0,0,0,D 2RVE-36 shut; 2RVE-102 open LOA ARV131,0,0 D 3
#1 DG fails to start MAL DSGIA ACT,0,0,D ACB 2E10 fails as is BKR HIV112,0,D e...............................
Insert: Prevents 2IAC-MOV130,133,134 SET JVO7AUTC(43)=3000 from auto closing on CIA. Valves can SET JV07AUTC(30)=3000 be manually closed SETJV07AUTC(29)=3000 Aligns CCP system LCV's and DCV's FILE LRTM41C
******************************** to match plant configuration
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Nuclear Power Division Training Administrative Manual DRILL 8-98-2 REV 1 PAGE2 OBJECTIVE l EXPECTED STUDENT RESPONSE l l INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l ARer PCS startup, insert .
~ANACK ANRSET FILE STUFFON FRZ Assign shin positions:
Simulator Frozen until after shift NSS turnover unless it needs to be on ANSS momentarily for an alignment change. RO PO STA Oncoming operators should complete the Conduct shin turnover with oncoming required checklists and carry out a formal operators. shin turnover. When the shin turnover is complete, Crew assumes control of the, unit. place the simulator to R,UN and Simulator running. , commence the drill. . Crew raises power in accordance with EVENT #1 2OM-52.4B @ step 2. Rate of rise is Power increase 10%/hr. G
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Nuclear Power Division Training Administrative Manual DRILL 8-98-2 REV 1 PAGE3 OBJECTIVE l EXPECTED STUDENT RESPONSE l l INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l PO verifies two condensate pumps in senice and dispatches operator to verify main feedwater pump recirc valves are in NSA ANSS directs PO to set desired load rate If requested, start tube oil pump for and load on EHC Control Panel 2FWS-P21 A Insert: LOA CFW381,0,D
******************************** PO depresses GO pushbutton on EHC panel to begin raising load PO monitors main generator for abnormal hydrogen gas temperatures RO maintains primary plant parameters Tavg within 2 degrees of Tref, axial flux within target band and control rods above their insertion limit PO maintains genei tor parameters within Power factor = .94 to .98 lagging the limits of the Calculated Capability Curve (Fig. 52-5) and maintains power factor Itd S eR_T PA GE s PO starts a second main feedwater pump
'Second feedwater pump is started 3A when total feed flow is 14000 to ye%
15000 M pph
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DUQUESNE L OMPANY Nuclear Power Division : Training Administrative Manual DRILL 8-98-2 REV 1 PAGE3A l INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l OBJECTIVE l EXPECTED STUDENT RESPONSE l NOTE: This evolution was added Transfer busses to offsite power prior ANSS directs PO to transfer 4kV busses during the scenario run because it was to starting 2FWS-P21 A 2A and 2B to offsite power to start felt we needed a Normal evolution for 2FWS-P21 A IAW 20M-36.4.C the Plant Operator in order to meet the requirements of ES-301. It was later determined, after the evolution was completed, that this was not the case. Credit could be taken for the PO actions during the load change. Therefore no other scenarios were modified PO verifies voltages approximately equal Allows for paralleling ofbusses PO places the Live Bus Transfer Switch to ON PO closes ACB 42A and verifies load is picked up 2A 4kV bus supplied from SSST PO opens ACB 42C PO closes ACB 142A and verifies load is
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picked up 2B 4kV bus supplied fro'm SSST PO opens ACB i42C PO turns Live Bus Transfer Switch to OFF Page 3A
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' r~~ ~ J{Vrs\ DUQUESNE Llu$m,)40MPANY - Nuclear Power Division Training Administrative Manual DRILL 8-98-2 REV I PAGE4 OBJECTIVE l EXPECTED STUDENT RESPONSE l l INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l When crew completes the 5% power . increase,insen EVENT #2 PO notes alarm, diagnoses SG pressure
- Channel 4 "B" SG steam pressure EVENT #2 channel problem, informs ANSS.
transmitter 2 MSS-PT486 fails low over 120 2 MSS *PT486 fails low. seconds. Insert: 2 MSS *PT486 indication drifts to 0 -
.....************************** psig.
XMT MSS 501,0,120,0,D Low steam pressure and pressure rate
******************************* status lights lit.
Loop 2 steamline pressure low / pressure rate high alarms. ANSS directs PO to take manual control "B" SG MFRV 2FWS*FVC488 modulates in response to steam flow of 2FWS*FCV488 and restore SG level to normal. and level signals. Crew refers to 20M-24.4.IF Attachment 4 for Instrument Failure. ANSS directs PO to select ChannelIII feed flow input to "B" SG level control.' , I i o
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p C'1 m -- L/ DUQUESNE LIEMOMPANY () - Nuclear Power Division Training Administrative Manual DRILL 8-98-2 REV 1 PAGE 5 OBJECTIVE l EXPECTED STUDENT RESPONSE l l INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l PO selects Channel III feed flow input to ChannelIII steam flow input "B" SG level control, and after the steam (2 MSS *FT485) to "B" SG level flow selector for Channel III is selected in control (located in Process racks). the process racks, places MFRV MFRV 2FWS*FCV488 in AUTO. 2FWS*FCV488 in AUTO and verifies "B" SG level restored to normal. proper response. ANSS identifies T.S. 3.3.2.1 applicability and directs crew to place channelin tripped condition within six hours. ANSS informs I&C ofsteam pressure When directed to trip bistables per Channel 3 Level must also be declared OOS due to sharing a common tap. channel failure. 2MSP-21.08-I on CF4, Slot 25, use the following: LOA PCS4 T,0,D Protection rack C4 door open. BST PCS801,0,D 2PS/486A (BS-1) tripped. Lo press SI BST PCS71 1,0,D 2PS/486B (BS-2) tripped. Hi rate SLI LOA PCS4 F,(,D Rack door closed. ANSS directs I & C to trip appropriate bistables. For Level Channel 3 bistables LOA PCS3 T,0,D Protection Rack C3 door open , RO/PO verifies operator in correct rack, 2LS/486A BS-1 La Ivi Rx trip BST PCS321,0,D monitorsbistabl~e trip evolution, informs BST PCS41 1,0,D 2LS/486C BS-2 HiIvl FWI ANSS upon completion. LOA PCS3 F,0,D Rack door closed PO returns 2FWS-FCV488 to Auto To switch Steam Flow to Channel 3: Primary Process Rack 7 SWI PCS8 2,0,D Selects position F484
p} p , DUQUESNE LIbjCOMPANY b Nuclear Power Division , Training Administrative Manual - DRILL 8-98-2 REV 1 PAGE 6 l INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l OBJECTIVE l EXPECTED STUDENT RESPONSE l After ANSS determines Tech. Spec. 3.3.2.1 requirements and shows intent to comply, continue with scenario. . EVENT #3 VCT Level Transmitter 2CHS-LTl12 fails high INSERT eseeeeeeeeeeeeeeeenseesseseeeeee XMT LDS21,100,0,0,D eeeeeeeeeeeeeeeeeeeeeeeeeeeeeees Ann. A4-2G, VCT Trouble alarms RO notes makeup is in progress either when it shouldn't be or has continued too long. , This transmitter failing high will cause Crew checks PCS to determine that an auto make-up to the VCT to begin if- LTl12 has failed high. , not in progress once enough letdown
-has been diverted away from the VCT. - ANSS references 20M-7.4.AAC, VCT i If a make-up is in progress, some time Level Hi-Hi; probable cause #2 may elapse before the RO notes that something is wrong. l Letdown diverted away from VCT and RO places the VCT level control switch in to Degasifiers and/or Coolant the VCT position Recovery Tanks
3 'gg (v) - DUQUESNE Llu(s,40MPANY (" ) Nuclear Power Division - Training Administrative Manual DRILL 8-98-2 REV 1 PAGE7 OBJECTIVE l EXPECTED STUDENT RESPONSE l l INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l
- RO checks LCVI12 and LCVIISA aligned to VCT RO takes manual control of LCVI12 and/or LCVI15 to divert letdown flow back to VCT and away from the Coolant Recovery Tanks EVENT #4 Once crew has control of VCT level continue 2RCS-P1444 fails high. If time permits, ANSS may refer to the following Technical Specifications:
Insert all of the following: High pressure deviation alarm, PRZR
...***************************** heaters turn off, spray valves open and 3.2.5 DNB Parameters ,
PORV 2CHS*PCV455C opens. RCS 3.4.1I PORVs , XMT RCS301,2500,0,0,D ' 3.3.3.5 Remote Shutdown Instrumentation VLV RCS32 2,0,C,PRC:444.GT.2400 pressure begins to drop rapidly. VLV RCS11 A4-lE, P0500D 1,0,0,C,RRCH535.LT.0.20 PORV sticks open, when block valve
.,****************************** is taken to closeit will fail oper: at 20 % .
RO notes alarm, informs ANSS and crew , INFO: , refers to ARPs ifnecessary. 2RCS*MOV535 is powered from MCC2-E06 Cu. SC. The heat trace associated with this PORV is 2 HTS-JB3-134, PNL N4AB Bkr. 4
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Nuclear Power Division - Training Administrative Manual DRILL 8-98-2 REV 1 PAGE8 OBJECTIVE l EXPEUIED STUDENT RESPONSE l l INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l PRZR control pressure low deviation ANSS directs PORV 455C be closed and alarm. master pressure controller be placed in A4-ID, P0501D manual. A4-1E, P0503D Possible OTDT mnback and rod stop. PO places master pressure controller in A4-48, T0517D manual, closes spray valves, and manually controls heaters. RO informs the ANSS that RCS pressure NOTE: Crew may decide to manually RCS pressure continues to drop. is still dropping with manual control of trip reactor prior to auto. trip setpoint. spray / heaters and that 2RCS*MOV535 indicated partially open before lights were lost. RO notes a reactor trip has occurred and Low PRZR pressure reactor trip annunciator actuates. informs ANSS. First Out: A5-4H, P0488D. Reactor trip RO and PO commence immediate actions ANSS enters and implements E-0 to , of E-0, ANSS references E-0 to verify ensure operator verification of reactor immediate actions. trip and SIS. 9 -
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DUQUESNE LIudOMPANY Q " Nuclear Power Division : Training Administrative Manual DRILL 8-98-2 REV 1 PAGE 9 OBJECTIVE -l EXPECTED STUDENT RESPONSE l l INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l RO verifies reactor trip. Steps 1 - 7 of E-0 are immediate Turbine trip due to reactor trip alarm actions. A5-6D lit. ' Rod bottom lights lit. Neutron flux dropping. RO/PO sounds standby alarm, announces Unit 2 reactor trip.
- NSS evaluates EPP. ,
It is not expected that the ANSS classify the event at this time due to being a 3 man crew PO verifies turbine trip. The following will fail the Off-site to Throttle or governor valves closed. 4kv breakers as is: Reheat stops or interceptors closed. BKR HIV2 2,0,D BKR HIV4 2,0,D PO ensures reheat steam isolation. BKR HIV7 2,0,D MSR supply block valves closed. BKR HIV10 2,0,D Depress reheater controIIer reset pushbutton. PO verifies generator trip. PCV-352 and 362 open. , ACB-4I open' . PO verifies power to AC emergency
~ 4KV busses A, B, C, D, AE and DF DF bus ene'rgized (2AE loses power). ~
busses. deenergized on auto bus transfer, DF ! re-energized via #2 EDG.
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D' DUQUESNE LIO[._jOMPANY Nuclear Power Division . Training Administrative Manual DRILL 8-98-2 REV 1 PAGE 10 OBJECTIVE l EXPECTED STUDENT RESPONSE l l INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l SI actuation status light dark, SI not RO checks if SI is actuated. actuated. Crew checks if SI is required. NOTE: depending on timing, plant may If RCS pressure < 1855 psig. not yet require an SI actuation SI required. SI actuated. RO/PO verifies SI. Actuated Immediate action steps completed. If SI is not actuated, transition will be to ES-0.1, " Reactor Trip Response," until Si occurs, at which time crew will return to E-0. PO checks diesel generators running. EDG 2-2 running PO verifies AFW status, informs ANSS 2FWE*P22 iunning,2FWE*P23B on clearance,2FWE*P23 A no power. that 2FWE*P23.A & B not running. TDAFW pump steam supply valves open. AFW throttle valves full open. RO verifies service water system in Two service water pumps running (one , service. per train). Service water header pressure 55-124 psig.
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DUQUESNE L1 OMPANY - 1 Nuclear Power Division - Training Administrative Manual DRILL 8-98-2 REV 1 PAGEI1 l PLANT STATUS OR RESPONSE l OBJECTIVE l EXPECTED STUDENT RESPONSE l l INSTRUCTIONAL GUIDELINES
. g/19/H RO and PO verify SI status.-
CRI J : rew closes CNMT HHSI pumps nmning. 4 isolation valves such that at least one HHSI flow indicated on 2 SIS-FI943. i valve is closed on each critical phase A LHSI pumps running. penetration before the end of the drill. Allindicating lights with red SIS marks lit. Note: Adverse CNMT values should be All indicating lights with orange CIA RO/PO verify CIA. : implemented if pressure > 1.5 psig. marks lit. 4 Allindicating lights with green FWI RO/PO verify feedwaterisolation. marks lit. CNMT pressure < 3 psig. RO/PO check if main steamline isolation j To trip 2FWE*P22 insert:
******************************** SLI not required. required.
MAL AFW3A ACT,5440,0,0,0,D RO checks CIB/ spray status. Alarm Al-2H dark. CNMT pressure < 8 psig. . . 2CCS-AOV118 opened. ' e station n PO establishes filtered water cooling to ! air compressor mnning. station air compressors. CCP pumps mnning. RO verifies CCP in service. j r eg te XAMIA>tt, O IS $QSk u)GS dALMd to N dot 0r$/cAl' becanu 5 coada,ne.e,J cond<+ians, i.m 14 Adu,x C04/ sew +
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- Nuclear Power Division - p Training Administrative Manual
--DRILL 8-98-2 REV 1 PAGE 12-l INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l OBJECTIVE 'l EXPECTED STUDENT RESPONSE l SR channels aligned properly. RO verifies source range detector high
- voltage switches in normal. i EVENT #6 Loss of heat sink criteria. Total AFW flow < 365 gpm. PO verifies total AFW flow not greater All SG NR levels < 5 [33]%. than 365 gpm, notifies ANSS of insufficient flow and SG levels.
i 4 ANSS makes transition to FR-H.1 and informs crew. It is not expected that the ANSS will NSS declares a Site Area Emergency j' make the EPP classification at this time within 15 minutes of entering FR-H.1 based on TAB (1.1 and L2), informs (3 man crew) crew, provides AA with notification form. RCS pressure > any non-faulted SG- RO/PO check if secondary heat sink is pressure. RCS hot leg temp > 350 F. ' required. - 2 of 3 SG WR levels > 8 [33]%. RO/PO check if feed and bleed should be PRZR pressure < 2335 psig. initiated.
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Training Administrative Manual' :- DRILL 8-98-2 REV 1 PAGE 13 OBJECTIVE - l EXPECTED STUDENT RESPONSE- l
'l INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l PDWST level > 80 in. ,
Crew tries to establish AFW flow at least - 2FWE*P23B OOS (P23 A - no one SG l power). ! 2FWE*P22 steam supply valves open. AFW throttle valves open. ; ANSS dispatches operator to locally if directed to investigate TDAFW pump investigate status of 2FWE*P22. -l status, report that the trip throttle valve is mechanically bound and you will need maintenance assistance to correct problem. ANSS contacts maintenance for work on 2FWE*P22 RCPs stopped. RO stops all RCPs and places all PRZR' 2
- PRZR heaters in PTL. heaters in PTL.
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SG blowdown and sample isolation PO checks SG blowdown isolation status. , valves closed. 2CNM-P21 A not running. PO checks if any condensate pumps are CT #2 - Crew establishes feedwater , FW isolation valves closed. mnning. flow into at least one SG before RCS
- feed and bleed is required.
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DUQUESNE LIGFTr COMFANY Nuclear Power Division g Training Administrative Manual DRILL 8-98-2 REV 1 PAGE 14 l INSTRUC joNAL GUIDELINES l PLANT STATUS OR RESPONSE l OBJECTIVE l EXPECitu STUDENT RESPONSE ' l 2CVS-P21 A,B PTL. RO isolates CNMT vents and drains, 2DAS-P204A,B stopped. resets SI. 2DGS-P21 A,B PTL. Both trains SI reset. Actuation status light A12-lD dark. ( Block status light A12-lC lit. Both trains CIA and FWI reset. ' RO resets CIA and FWI. 2FWS*HYV157A,B,C open. RO opens MFW CNMTisolation valves. When desired to return 2FWE*P22, 2FWS-P21 A not running, feed flow Cre.y starts either the startup feed pump via bypass FRVs not available. or A main feed pump. insert: MAL AFW3A CLR LOA AFW221,0,D All SG NR levels < 5 % [33]%. PO checks SG levels. ANSS returns to E-0 and informs crew: i After flow is established from Aux - Feed Tavg maybe dropping due to feed RO checks RCS Tavg stable at or trending flow. to 547 F. No other steam dumping in progress. 0
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- DUQUESNE LIO -
Nucle:r Power Division - Training AdministrativeManual :' DRILL 8-98-2 REV 1. PAGE 15 = l PLANT STATUS OR RESPONSE l OBJEC11VE- l EXPEC1ED STUDENT RESPONSE l INSTRUCTIONAL GUIDELINES l-Available personnel perform ESF checklists. No recirc spray pumps ninning. RO checks recirc spray status.- PORVs closed (not leaking). RO checks Pressurizer isolated. Spray valves closed. l t Safeties closed (PSMS data). PRT conditions normal. . RCN not running. RO checks ifRCPs should be stopped. l i i No SG pressure dropping PO checks if any SGs are fauhed. : uncontrollably or completely
' depressurized.
t No SG levels rising uncontrollably. Crew checks if SG tubes are intact.' ; l Secondary radiation levels normal. C,NMT parameters reflect SBLOCA , Crew checks CNMT conditions consistent ' with pre-event values. j conditions. - I i ANSS makes transition to E-1 Step 1 and l informs crew. l i
DUQUESNE Llu OMPANY - " [ Nuclear Power Division : " Training Administrative Manual
-g DRILL 8-98-2 REV 1 PAGE 16 EXPECTED STUDENT RESPONSE - l f l PLANT STATUS OR RESPONSE l OBJECTIVE l l INSTRUCTIONAL GUIDELINES .
Crew checks control room habitability.- Control room radiation normal. CIB has not occurred. CREBAPS not required. RO checks if RCPs should be running. No RCPs running. , No recirc spray pumps ruming. RO checks recirc spray pump status. t-RO verifies both CNMT H2 analyzers CNMT sample amber lights lit. running. i PO checks if any SGs are faulted. SG pressures normal. I SG NRlevels depend on rate offeed PO checks intact SG levels. flow, maintain 5[33]-50%. Power available to block valve. RO checks PORVs and block valves. PORVs closed. At least one MOV open. , 4 N v 4
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l ..- DUQUESNE LItcuar COMPANY V Nuclear Power Division . Training Administrative Manual DRILL 8-98-2 REV 1 PAGE 17 INSTRUCTIONAL GUIDELINES - l PLANT STATUS OR RESPONSE l OBJECTIVE l EXPECTED STUDENT RESPONSE l l Note: Due to possible RCS cooldown RCS subcoolihg > 41[59] F. RO/PO check if SI flow can be terminated. due to feedwater flow rate, PRZR level Feed flow > 365 gpm or NR level > may not met SI termination cri. ;ia;if 5[33]%. so, monitor crew progress in E-1 to RCS pressure stable or ris ng. Step 12, where a check on RCS PRZR level > 4[42]%. pressure should yield a return to Step 2. When feed flow is reduced, RCS parameters will recover and meet SI termination criteria. ANSS makes transition to ES-1.1 and informs crew. Previously isolated. RO isolates CNMT vents and drains system. Previously reset. RO resets SI (both trains). Previously reset. RO resets CIA and CIB (both trains).
. RO secures HHSI pump.
Terminate scenario after one HHSI pump is secured per ES-1.1. Collect and review logs after allowing Crew logs should be accurate clear and concise. crew time to complete. , NOTE: The expected EPP declaration is a SITE AREA EMERGENCY on Tabs 1.1.1 and 1.2.1. e
l 'l r g Appendix D Scena6 Outline Form ES D-1 Facility: _Bgever ValjigyAyv.or_Sta.ligo UniL2. Scenario No.: 3 Op-Test No.: _2 LOT 2A l Examiners: Operators: l Objectives: To evaluate the aoolicants abili ty to use Normal. Abnormal. Emeroencv. and Alarm Resoonse orocedures to raise reactor oower. and to resoond to a turbine EHC system malfunction resultina in a loss of load. a trio of the in seryigg Doric Acid Transfer oumo. to a failure of a source ranae detector. an automatic Turbine trio failure. and a steam break affectina all 3 steam aenerators with subseauent failure of an automatic steam line isolatig!L Initial Conditions: The olant is at 48% oower. steady s. tate conditions. and has iust been released by system to raise oower to 100%. The Startuo Feedwater oumo and one Motor Driven Aux Feedwater oumo are oos. Rods are in Manual. Tumover. System has released the Unit to retum to 100% oower. l2FWS-P24) and [2FWE*P2381 are OOS. Event No. Malf. No. Event Event Type
- Description 1
N/A R R0 Raise Reactor Power N-POI SRO 2 CLF-XMT i 2RCS*LT459 fails high; Tech Spec entry RCS 19 RO/SRO
/^\
j() 3 HC6 reactor power PO/SRO 4 F PMP C Boric Acid Transfer Pump trips after RO reduces power by 5%. Tech Spec entry RO M 5 MAL MT Steam Line break affecting all three generators in the Main Steam Valve Room MSS 2A, R0/P0/ 2_B, 2C SRO 6 MAL C Auto Turbine Trip Failure EHC8A P0/SRO 7 Oyerride C Auto and manual Steam Line Isolation signal fails. Components must be [,$g R0/P0/ manually positioned Status lights 8 MAL I N 31 failed low - will not respond v.tien auto actuated NIS1A RO/SRO
* (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor l (("%)
I %J l NUREG-1021 1 of 2 Interim Rev. 8, January 1997
i' Scenario #3 summary description. Unit 2 is at 48% power preparing for an increase in power to 100% in accordance with normal operating procedures. After a 5% power increase, Pressurizer level transmitter 2RCS*LT459 will fail high requiring manual operator action to control level. This will require entry into Tech Specs. This will be followed by a failure in the EHC turbine controller Valve Position Limiter resulting in a Load Rejection. After reactor power has been reduced several percent to match turbine load, the Boric Acid Transfer Pump will fail. Once the crew has determined the proper course of action for this failure, a Steam Break affecting all 3 steam generators will l occur in the Main Steam Valve Room. There will be an auto Turbine Trip failure built in, requiring a manual Turbine Trip. There will also be an automatic and manual Main Steam Line Isolation Signal failure built in requiring the operators to manually re-position components. Post trip there will he a failure of Source Range Detector N-31. The scenario will be terminated when the crew stabilizes the plant in ECA-2.1, Uncontrolled Depressurization of All Steam Generators. ( I I i f LO l 2 of 2
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Beaver Valley Power Station Unit 1/2 1/2OM46.1.C i CONDUCT OF OPER ATIONS Issue 4 Revision 3 (~]
%J ORGANIZATIONAL AND RESPONSIBILITIES OF THE OPERATIONS GROUP Page C 7 of 28 SHIFT TURNOVER AND RELIEF -
Figure 48.1.C-2, Assistant Nuclear Shift Supervisor Shift Turnover Checklist flecord fype A%.N LT s Assistant Nuclea,r shift SupeM sor .BVPS Unit No. SHWT TORMOVER CHECKLIST 0000 1600 2400
- 1. Oncoming and ongoing ANSS conduct a rev6ew of the centrol beards obserung evolubons in progress, 0 0 0 unusual equipment or systems status and any unuseat alarms er ind6catsons or status lights.
- 2. Rowew pronous shift narrative less. (oncoming) 0 0 0
]
- 3. Discuss any identified tre,wls that require special attentien 0 0 0
- 4. Descuss any temporary togs, parameter trending or temporary procedures in effect. O O O' 5 Review MSPs, OSTs. SVTs, PMPs (or other procedures aNecisag control room indicabons)in progress or 0 0 0 1 n(heduled (oncoming).
- 6. Discuss any gas or liquid discharges in progress. O O O T. Ust on reverse any Technical Specificaten items in eftect (by ongoing). Review list (oncoming). O O O
- 8. Vertfy normal shift complement and emergency agead seguirements are met (oncoming). O O O
- 9. Review the Clearance Program for posted and signed en clearances. O O O l
- 10. Review the current Equipment OOS comseter tracadas log printout (oncoming). O O O l
- 11. Review the ESF Mimic Print for out of nennel m s(encamingh w 0 0 l
[N 12. Discuss status of procedures in progress, being tumed over. O O O k
%/ 13-
- a. Circle the priority traintt N/A for all modes other than A or B A er B A Or 6 Modes 5 and 6
- b. Vertfy Normal and emergency power to priertly trale N/A for all modes other than N E NE NE ~
Modes 5 and 6 00 00 0 0
- 14. The Nuclear Control Operators narratNe leg; St 4, S,6; or the NOMS Narrathre log (dependent on which 0 0 0 is in use), has been rewtowed to assure all sign 64 cant items have been listed with adequate description.
- 15. Oncoming ANSS, log rrve (5) qualified fire brigado members in the ANSS tog; S 16,1F.18. If in use. O O O
- 16. The offgoing ANSS signature certifies that their narrattwo log entries and the tour tog entrtes made on 0 0 0 their shift aris accurate, clear, concise and complete and that they have been property retteved.
- 17. The offgoing ANSS prints out current copies of the Equipment OOS computer trackJng tog and distnbutos O O O to each watch stafson.
(Offgoing) (Oncoming) (Signature) Date/ Time (Signature) Date/ilme (Signature) Date/ Time (signature) Date/ Time (Signature) Date/ Time (Signature) DateITime
- 18. The oncoming ANSS has rewlewed the approved Control Room copy of the OST schedule.
(Unit 2 L.ER 90403) (Signature) (Signature) (Signature) . fD (Example . FitONT) l t
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l FOR TRAINING USE ONLY
a A *.a 59 w sa,Aa-.4 .,,4a.. 4 14.a A h J J A + A .. . _ a 4 - _ t Beaver Valley Power Station Unit 1/2 1/20M-48.1.C CONDUCT OF OPERATIONS Issue 4 Revision 3 ORG ANIZATIONAL AND RESPONSIBILITIES OF Tile OPS. GROUP Page C8 OF 30 ( '( SlilFTTJRNOVER AND RELIEF l
.1 TECII SPEC ACTION ITEMS IN EFFECT (Soccial Surveillence Below)
Component / T. S. No. Daterrime Date/ Time Daterrime System Applied Due Complete
- 1) 2FWE*P23B 3.7.1.2.c Today -6 hrs ago 66 hours from now
- 2) 2FWS-P24 INFO l
l 1 l l l
,r' REMARKS: 00-08 , Q) l. Pump bearing replacement in progress. 2FWE*P22 aligned to 'B' header with 2FWE*36 shut and 2FWE* 102 open.
- 2. Info only - maintenance on speed increaser REMARKS: s8-16 REMARKS: 16-24 i
(EXAMPLE)
- p., FIGURE NO. 48.1.C-2
, (%)' Figure 48.1.C.2, Assistant Nuclear Shin Supervisor Turnover Checklist
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Nucicar Power Division Training Administrative Manual f. 8-98-3 (iii)REV1 RCS boron - 870 PPM, CBD = 171 steps. Reactor power @ 48 % i INITIAL CONDITIONS IC 42 ~ STICKERS VOND MARKINGS l , ' ADDITIONAL LINEUP CHANGES ? Red Danger Tag 2FWE*36 shut 2FWS-P24 OOS - Pull-to-Lock Red Danger Tag 2FWE*102 open
~2FWE*P23B OOS - Pull-to-Lock 2FWS-MOV152 - De-energized Red Danger Tag 2FWE*38 shut DATE/TlhE TTS# AND TINE LIMIT EOUIPMENT STATUS i
' MARK Today - 6 hours ago 3.7.1.2.c - 72 hour time limit [
2FWE*P23B 2FWE*P22 aligned to 'B' header INFO 2FWE*36 shut; 2FWE*102 open : 2FWS-P24 SHIFT TURNOVER INFORMATION
- 1. Crew is to raise power in accordance with 2OM-52.4B, Part A. Previous shift completed QPTR 20ST-2.4.A sat.
- 2. 2FWE*P23B OOS for pump bearing replacement. Expected to be returned in 18 hours. 2FWE*P22 aligned to 'B' header.
- 3. 2FWS-P24 OOS for speed increaser maintenance.
- 4. CCP System - LCV's controllers are disconnected on VB'C'. Valves are controlled in auto from the process racks. DCV's are in mancal to reduc
" hunting" and possible valves leakage.
SCENARIO SUPPORT MATERIAL OM 1/2.48.1 Figure C-2 (ANSS Turnover Checklist) 20M-52.4B, Iss.1 Rev. 30, signed off to step 2. Reactivity plan for stanup. INSTRUCTIONAL METHODS NOTES There shall be no direct intervention or assistance by the simulator instructor. Terminate the drill when directed by the exam team. b 9 i
R. .. f' DUQUESNE LIut._40MPANY " ' Nucle r Power Division Training Administrative Manual DRILL 8-98-3 REV 1 - PAGE 1 OBJECTIVE l EXPEC1 tid STUDENT RESPONSE -l l INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l
' Initialize the simulator at IC -42 Reactor plant at 48% equilibrium conditions. The unit is to return to full power at 10%/hr. Boron is 870 ppm and Bank D is at 171 steps.
- f All necessary notifications have been j
made and permission to increase load has been received. QPTR 20ST-2.4.A completed sat. Procedure in effect is 20M-52.4B Load Follow, Part A. Insert: FILE LRTM4IC Aligns CCP system LCV's and DCV's to match plant configuration
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m . r ,, . ) 1 ('%. y) (' )8 DUQUESNELIM. ,40MPANY Nuclear Power Division Training Administrative Manual DRILL 8-98-3 REV 1 PAGE 2 OBJECTIVE l EXPECIeD - NT RESPONSE l
.l INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l Insert:
......+.........................
SWI PPL37 ACT,2,0,D This will prevent auto and manual SWI PPL38 ACT,2,0,D Main Steam line isolation. SWI PPL39 ACT,2,0,D Components willhave to be manually SWI PPL40 ACT,2,0,D re-positioned BST PCS66 2,0,D BST PCS67 2,0,D BST PCS63 2,0,D BST PCS69 2,0,D BST PCS70 2,0,D BST PCS712,0,D BST PCS72 2,0,D BST PCS73 2,0,D BST PCS74 2,0,D BST PCS75 2,0,D BST PCS76 2,0,D BST PCS77 2,0,D BST PCS78 2,0,D BST PCS79 2,0,D BST PCS80 2,0,D BST PCS812,0,D BST PCS82 2,0,D BST PCS83 2,0,D Insert:
******************************** Prevents Auto Turbine Trip. Manual MAL EHC8A ACT,0,0,D will work. '
4 6 __. ______ _ _m..__. _ _ _ _ _ . _ _ . _ _ _ _ _ _ _ _ . _ _ . . _ _ _ _ . _ . . . _ _ _ - _ _ _ _ _ _ _ _ _ . _ . _ _ _ _ . _ _ _ _ _ __ _ -_._ . _ ___
f'- -( ) [m! DUQUESNE LIK 40MPANY ^ Nuclear Power Division Training Administrative Manual . DRILL 8-98-3 REV 1 PAGE 3 OBJECTIVE l EXPECiED STUDENT RESPONSE 'l l INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l Insert:
******************************** Source Range Detector N31 failed MAL NIS1 A ACT,1,0,0,0,D low.
Insert: LOA HIV711,0,D 2FWE*P23B OOS LOA AFW3 0,0,0,D ' 2FWS-P24 recirc valve failure VLV CFW271,0,D 2FWS-MOV152 de-energized shut VLV CFW451,0,D 2FWE*P22 aligned to 'B' header LOA AFW10,0,0,D 2FWE-36 shut; 2FWE*102 open : LOA AFW131,0,0,D After PCS stanup, insert ANACK - ANRSET FILE STUFFON FRZ i Assign shift positions: NSS Simulator Frozen until after shift ANSS turnover unless it needs to be on momentarily for an alignment change. RO PO STA Oncoming operators should complete the Conduct shift turnover with oncoming required checklists and carry out a formal operators. shift turnover.
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(/ DUQUESNE Liu JOMPANY - Nuclect Power Division Training Administrative Manual DRILL 8-98-3 REV 1 PAGE 4 OBJECTIVE l EXPECTED STUDENT RESPONSE l l INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l When the shift turnover is complete, Simulator running. Crew assumes control of the unit. place the simulator to RUN and commence the drill. PO verifies two condensate pumps in EVENT #1 service and dispatches operator to verify main feedwater pump recirc valves are in Power increase.
******************************** NSA ANSS directs PO to set desired load rate If reguested, statt tube oil pump for and load on EHC Control Panel 2FWS-P21 A Insert:
LOA CFW381,0,D PO depresses GO pushbutton on EHC panel to begin raising load PO monitors main generator for abnormal hydrogen gas temperatures Tavg within 2 degrees ofTref, axial RO maintains primary plant parameters flux within target band and control rods above theirinsertion limit O t
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!Y DUQUESNE Llui.,,jOMPANY Nucles Power Division Training Administrative Manual DRILL 8-98-3 REV 1 PAGE 5 INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l OBJECTIVE l EXPECIED STUDENT RESPONSE l l
Power factor = .94 to 98 lagging PO maintains generator parameters within the limits of the Calculated Capability Curve (Fig. 52-5) and maintains power factor Second feedwater pump is started PO starts a second main feedwater pump when total feed flow is 14000 to 15000 M pph After 5% power increase, insert event EVENT #2 RO notes alarm and informs ANSS Insert: 2RCS*LT459 fails high.
******************************** A4-2B Pressurizer level high alarm XMT RCS191,100,0,0,D e...............................
ANSS may refer to the ARP or the RO determines that 2RCS*LT459 has Instrument Failure Procedure. failed high and informs ANSS ANSS goes to IF procedure Attachment 1 ANSS directs RO to place the PRZR Level Control Channel Selector in position II & III ANSS directs RO to ensure Level recorder is selected to an operable channe!
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DUQUESNE LIEJOMPANY '
. Nuclear Power Division .
Training Administrative Manual
. DRILL 8-98-3 REV 1 PAGE 6 INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE ' l OBJECTIVE l EXPECTED STUDENT RESPONSE l l l
RO ensures Heater Groups are operating as desired RO positions FCV122 as needed TS 3.3.1.1 Rx Trip Instrumentation ANSS refers to Technical Specifications TS 3.3.3.5 Remote S/D 1 t Instrumentation TS 3.3.3.8 Accident Monitoring Instrumentation To trip bistables per 2MSP-6.23-I ANSS notifies I&C of failure and the need , Card Frame 4, slot 42 to trip the High Level bistable for LT459 Insert:
.....................e.e....ee .
LOA PCSI T,0,D Prot. Rack Cl door open ' BST PCS971,0,D 2LS/459A-1 BS-1 LOA PCSI F,0,D Rack door closed
..... .eeeeeeeeeeeeeeeesseseeese
. 2-3 minutes after plant is stabilized, insert the following event t
+
EVENT #3 ~ Insert: Turbine load rejection of t
******************************** approximately 20% '
. 3 MAL EHC6 ACT,18,0,0,D ,
1 PMP BATI 2,0,D Boric Acid Transfer pump will trip if
******************************** running or on next start b
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Nudr rawer Division Training Administrative Manual DRILL 8-98-3 REV 1 PAGE 7 INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l OBJECTIVE l EXPEC1ED STUDENT RESPONSE l l Load rejection to 18% limiter position Crew recognizes load rejection, monitors plant for any subsequent unexplained load (100 - 150 MW). RCS temperature rises Tavg-Tref, SG reductions. flow mismatch, SG level deviation alarms. Condenser steam dumps open. Load rejection 15 - 50% status light. ANSS refers to AOP-2.35.2. A4-3C, T0507D A6-9F, F0475D A6-10F, F0476D A6-1 IF, F0477D Tavg dropping to Tref. RO checks operation of auto rod control / manually reduces Tavg via rod insertion or boration. RO sounds standby alarm and announces Unit 2 load rejection. Governor vafves, main generator, and Crew checks governor valve closure output PCBs norma; for current sequence, verifies breaker positions and conditions. main generator output. Crew determines the valve position limiter Note: Crew response to valve position to be the problem. limiter as root cause is not part of AOP implementation. 9
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(,) DUQUESNE LI OMPANY - ], , - Nucle:r Power Division Training Administrative Manual DRILL 8-98-3 REV 1 ~ PAGE 8 INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l OBJECTIVE l EXPECTED STUDENT RESPONSE l l PO notifies the system operator ofload , loss. When and if RO tries to borate, the previously installed command will trip the Boric Acid Transfer Pump 2CHS*P22A shaft seizure (if running or upon next start). 2CHS*P22A' RO recognizes problem, inform ANSS, indicates tripped. Boric Acid to and refer to ARP A2-2F. Blender Deviation alarm. Boric acid pump thermal overload trip. A2-2F, Y0140D , ANSS directs plant operator to - investigate. Inform crew that the pump tripped on . thermal overload. NSS determines that T.S. 3.1.2.2 and ' 3.1.2.6 are applicable, and informs creiv and/or management of 72 hour action statement requirements. ANSS directs alignment of"B' Boric Acid
' Storage tank in accordance with 20M-7.4.P f
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('"'T- - Nucle:r Power Division Training Administrative Manual DRILL 8-98-3 REV 1 PAGE 9 OBJECTIVE l EXPECTED STUDENT RESPONSE l l INSTRUCTIONAL GUIDELINES - l PLANT STATUS OR RESPONSE l Tavg-Trefwithin 5 F. Crew checks Tavg-Trefwithin 5 F, resets Load rejection bistables reset. steam dump controller. EVENT #4 Steam Break in the Main Steam Valve The following malfunctions cause a room affecting all 3 Steam Generators simultaneous depressurization of all 3 SGs Insert: , MAL MSS 2A ACT,6E+05,0,0,0,C,JDUM100 MAL MSS 2B ACT,6E+05,0,0,0,C,JDUM100 MAL MSS 2C ACT,6E+05,0,0,0,C,JDUM100 SET JDUM100=T i I g
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DUQUESNE LIui._).,OMPANY Q ' Nuclear Power Division Training Administrative Manual DRILL 8-98-3 REV 1 PAGE 10 - l PLANT STATUS OR RESPONSE l OBJECTIVE l EXPECTED STUDENT RESPONSE l l INSTRUCTIONAL GUIDELINES Increased steam. flow indication, PO notices abnormal SG and RCS decreased SG pressures. parameters, informs ANSS. SG level transients (swell effects), associated alarms. Increasing reactor power, decreasing Tavg, PRZR pressure and level, associated alarms. High temperature not due to vent fan trip (A10-3F not lit). Main steam valve area temperature high. NOTE: Crew may opt to manually trip A10-4F, T2855D plant due to excessive RCS cooldown NSS/ANSS directs operators to shutdown and definite plant damage. If trip is using AOP 2.51.1 (emergency shutdown). performed, monitor E-O actions while continuing with scenario. Load decrease commenced. NSS evaluates EPP. SIS actuation will occur due to low pressurizer pressure. Crew infonns System Operator that plant will be shutting down at 5% per minute. RO maintains Tavg within 5 F ofTref. Operators coordinate load reduction at 5% per minute.
40MPANY
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DUQUESNE Llu ,, Nucle:r Power Division _ Training Administrative Manual
- drill. 8-9S-3 s
REV 1 PAGE II
- OBJECTIVE l EXPECIED STUDENT RESPONSE l.
.l' INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l
- Below P-9 a turbine trip does not RO ensures one PORV in auto with its
. produce a reactor trip. associated block valve open.
RO informs ANSS of reactor trip. RCS Tavg, PRZRlevel, SG pressures RO and PO commence immediate actions ofE-0, ANSS references E-O to verify dropping. immediate actions. Steps 1 - 7 of E-O are immediate actions. Turbine trip due to reactor trip alarm RO verifies reactor trip. A5-6D lit. Rod bottom lights lit. Neutron flux dropping.
~
RO sounds standby alarm, announces Unit 2 reactor trip and SI. 1 9 +
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DUQUESNE Llo__40MPANY b - Nuclear Power Division Training Administrative Manual DRILL 8-98-3 REV 1 PAGE 12 OBJECTIVE l ' EXPECTED STUDENT RESPONSE l l INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE ' l NSS evaluates EPP and declares an
-It is not expected that ANSS will .
Unusual Event due to Main Steam Line ; classify the event at this time (3 man Break (Tab 2.10). crew) Throttle and governor valves open. PO checks turbine tripped. EVENT # 6 Reheat stop and intercept valves open. PO reports that no Throttles or Governor . i and Reheat stops or Intercept valves are Main Turbine Fails To Automatically not closed. [ Trip. P Throttle and governor valves are PO MANUALLY trips turbine, verifies closed. turbine trip valves close and reports , Reheat stop and intercept valves are actions to ANSS. closed. ; I MSk steam supply block valves PO ensures reheat steam isolation closed. i Reheater controller reset pushbutton depressed. . Main generato'r output breakers open. PC verifies generator trip. Exciter circuit breaker open. 2AE and 2DF busses energized. PO verifies power to AC emergency busses. 9 4
.m _ ._ - - _ _ . _ . . . _ . _ _ _ -
_..____..-_______.m.___..___-.____m_.. _ _ . . _ _ _ _ _ _ _ . _ _ . _ _ _ _ _ _ _ _ _ _.___________ _ ___ _ _ _ - -* --_
w f DUQUESNE LIu(~'s.s ,40MPANY ~) - Nuclear Power Division - Training Administrative Manual DRILL 8-98-3 REV 1 PAGE 13 l INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l OBJECTIVE l EXPEUIED STUDENT RESPONSE [ Immediate actions completed. Any SI annunciator. SI actuation - RO checks if SIis actuated. status light. EDGs running. PO verifies EDGs running.. 2FWE*P23B (OOS) PO recognizes failure of 2FWE*P23B not MDAFW pump 2FWE*P23B failed 2 MSS *SOV105A-F open. running and reports condition to ANSS. 2FWE*HCV100A-F open. Two service water pumps running (one RO verifies senice water system in per train). senice. Service water header pressure 55 - 124 psig. HHSI pumps running. RO verifies SI status. HHS1 flow indicated. LHSI pumps running. SI valve alignment - allindicating lights with red SIS marks lit. CI A actuated, all indicating lights with RO/PO verify CIA. orange CIA marks LIT. , Allindicating lights with gre.n FWI RO/PO verify FWI. marks lit. 4 h
..-_.____.._..__c _ ____ m_s __ _ . . - .i_.__ ..m_____-_...___._m..___.__._____._..____.._.____-____.___.__.__:__._.a______.__ :. __._m__ __ _._____.-_ _ _
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(V DUQUESNE LIu!.s,20MPANY (,) Nuclear Power Division Training Administrative Manual DRILL 8-98-3 REV 1 PAGE 14 INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l OBJECTIVE l EXPECTED STUDENT RESPONSE l l EVENT #7 MSLI actuated, all indicating lights RO/PO checks if main steam line isolation with yellow MSLI marks LIT. is required, verify MSLI did not occur, tries manual MSLI, and then manually Automatic and Manual Main Steam closes valves. Line Isolation Fails. Crew must manually manipulate valves. CIB alarm not lit. RO checks CIB/ spray status. Containment pressure < 8 psig. 2CCS-AOV118 opened. One station PO establishes filtered water cooling to air compressor running. station air compressors. CCP pumps running. RO/PO verify CCP in sersice. SR channels aligned properly. RO verifies SR detector high voltage switches in normal. AFW flow > 365 gpm. PO verifies AFW flow greater than 365 gpm. Tavg less than 547 F and dropping RO checks RCS Tavg stable at or trending rapidly. to 547 F. Steam dumps closad, SLI initiated. Cooldown due to faulted SGs. 9 4 4
(d, DUQUESNE Llm.sOMPANY Nuclear Power Division Training Administrative Manual DRILL 8-98-3 REV 1 PAGE 15 - OBJECTIVE l EXPECTED SRJDENT RESPONSE l l INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l ANSS directs personnel to perform emergency safety fun tion checklists. Recirc spray pumps not running. RO checks recirc spray pump status. PORVs closed (not leaking). RO checks PRZRisolated. Spray valves closed. Safeties closed (PSMS data) PRT conditions normal. RO checks ifRCPs should be stopped. RCPs running PO checks if any SGs are faulted. All SGs faulted. ANSS makes transition to E-2 and informs crew. STA monitors status trees. Control room habitability system not ANSS verifies control room habitability. required. All indicating lights with yellow SLI RO/PO verify steamline isolation. mark closed.
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_ . - - _ . . - - _ - - . _ _ _ _ _ _ _ . . _ _ _ . . _ - . - . _ _ - _ _ _ _ _ - . - - - _ _ _ - - _ _ _ - - . _ - . . -_ J
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Nuclear Power Division
. Training Administrative Manual DRILL 8-98-3 REV 1 PAGE 16 OBJECTIVE l EXPECTED STUDENT RESPONSE l PINSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l All SG pressures droppingin an Crew checks for any non-faulted SGs.
uncontrolled manner. ANSS makes transition to ECA-2.1 and informs crew. All SG pressures dropping. PO checks all SG pressures. 2CVS-P21 A,B in PTL. RO isolates CNMT vents and drains, 2DAS-P204A,B in stop. resets SI, CIA, CIB. 2DGS-P21 A,B in PTL. Both trains SI reset, A12-lC lit, Al2-ID not lit. Both trains CIA reset, CIB not actuated. 2FWE*P23B running. Crew checks secondary pressure When directed to locally close steam 2FWE*P22 tripped. boundary. supplies to TDAFW pump, wait an appropriate delay then report that the 2 MSS *SOV105A-F open. ~ main steam valve room is not' accessible All yellow SLI marks lit. All green FWI marks lit. , 2SVS*PCV101 A,B,C shut. 2SVS*HCV104 shut. 2BDG*AOV100Al,B1,Cl shut. 9
OMPANY U DUQUESNE .1
- Nuclear Power Division -
Training Administrative Manual DRILL 8-98-3 REV 1 PAGE 17 INSTRUCTIGNAL GUIDELINES 'l PLANT STATUS OR RESPONSE l OBJECTIVE l EXPECTED STUDENT RESPONSE 'l '!
.l CRITICAL TASK - Crew controls the . AFW flow to approximately 50 gpm to PO contro!s feed flow to minimize RCS
' AFW flowrate to > 50 but < 100 gpm each SG, RCS hot leg temperatures cooldown.
dropping. ; per SG in order to minimize the RCS ~ cooldown rate before a severe (orange) challenge develops to the integrity CSF. _ Three RCPs running, RCS to SG D/P . RO checks if RCPs should be stopped. [ NOTE: at flows < 70 gpm, SPDS and CCP flow satisfactory. g indication may go to zero. _ Power available to block valves. RO checks PRZR PORV and block valves. l PRZR PORVs closed. Block valves : open with associated PORVs in service. No SG levels rising uncontrollably. Crew checks if SG tubes are intact. Secondary radiation consistent with pre-event values. - RCS pressure > 185 psig and staole. RO checks if LHSI pumps should be LHSI pumps stopped and in auto. stopped, secures pumps and places them in j auto. t CNMT spray not actuated. ANSS checks if CNMT spray should be stopped. i RWST level > 460 inches. RO checks RWST level. i i
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' DUQUESNE L1 OMPANY Nucle:1 Power Division Training Administrative Manual DRILL 8-98-3 REV 1 PAGE 18 l INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l OBJECTIVE l EXPECTED STUDENT RESPONSE l
. RCS hot leg temperature greater than RO checks if SI accumulators should be 390 F. isolated.
ANSS checks ifSI flow should be ! RCS subcooling > 41 F. RCS pressure stable. PZR level > 4%. . terminated. 2J and 2K busses energized. PO verifies power available to station and CNMT instrument air compressors. , P Station air compressor mnning, header PO checks station air status. pressure greater than 70 psig. Supply valves 2IAC-MOVl31 and PO establishes instrument air to CNMT.
*MOV130 opened. CNMT air ,
pressure > 85 psig. CRITICAL TASK - Crew secures one HHSI pump, aligns normal charging and ' letdown when SI termination criteria are met and before rupture of the PRT , One HHSI pump secured. RO stops one HHSI pump. j mpture disc. RCS subcooling > 41 F. RO verifies SI flow not required. PRZR level > 4%.
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m m . ( ) # . DUQUESNE LIGai COMPANY Nuclear Power Division Training Administrative Manual DRILL 8-98-3 REV 1 PAGE 19 _ INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l OBJECTIVE l EXPECTED STUDENT RESPONSE l l 2CHS*FCV122 closed. RO establishes normal charging flow. 2CHS*MOV289,310 opened. i 2CHS*FCV122 adjusted. 2 SIS *MOV867A - D closed. RO closes HHSI to cold leg MOVs. t RO controls charging flow to maintain PRZRlevel stable or rising. i LHSI pumps presiously stopped. RO stops LHSI pumps and place in auto. SI recirc mode reset. RO resets SI recirc mode (both trains). RCS subcooling > 41 F. RO verifies SI flow not required. PRZR level > 4%. Hot leg temperatures dependent on RO checks RCS hot leg temperature stable i conditions. or dropping. NR levels < 50%. PO checks SG narrow range levels < 50%. 4 I i
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Nuclear Power Division Training Administrative Manual DRILL 8-98-3 REV I PAGE 20 OBJECTIVE l EXPECTED STUDENT RESPONSE l
. l- INSTRUCTIONAL GUIDELINES - l' PLANT STATUS OR RESPONSE l_
RO checks ifletdown can be established, PRZR level > 14%. CCP pumps running. then establishes letdowm. Letdown rad monitor consistent with , pre-event values. 2CHS*FCV122 adjusted to 30-50 gpm , flow. 2CHS*AOV204 openei 2CHS*PCV145 in manual and 50% , open.
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2CHS*LCV460A,B opened. 2CHS* AOV200A,B, C opened as appropriate. 2CHS*145 adjusted to 260 psig and placed in auto. RO checks VCT makeup control system. Makeup control in auto and set to greater than RCS boron concentration. 2CHS*LCVI15C, E opened. RO aligns HHSI pump suction VCT. 2CHS*LCVIISB, D closed.
~ Terminate scenario after step in ECA-2.1 aligns charging pump suction to -
VCT. Operator logs sfiould be clear, accurate and concise. Collect and review logs after allowing operators to complete them. l S
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f~) DUQUESNE LludOMPANY 'r Nuclear Power Division Training Administrative Manual }
' DRILL 8-98-3 REV 1 PAGE 21 OBJECTIVE l EXPEcitD STUDENT RESPONSE l 5'l INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l Erase any vond markings associated .
.with this drill.
NOTE: The expected EPP declaration is an UNUSUAL EVENT - TAB .2.10. t s l i
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1 a Appendix D Scenario Outline Form ES-D-1 Facility: Beaver Vallev Power Station Unit 2 Scenario No.: 4 Op Test No.: 2 LOT 2A Examiners: Operators: Objectives: To evaluate the aoolicants ability to use Normal. Abnomial. Emeraencv. and Alarm Resoonse orocedures to resoond to a Main Feedwater Rea Valve oscillation. a oower ranae failure with rod control movement coincident with a stuck rod. a #1 seal failure on a Reactor Coolant Pumo regltina in a small break LOCA. and the failure of the Reactor to trio in both automatically and manually (FR-S.1 - ATWS). Initial Condtions: The plant is at 75% oower. steady state condtions. The Startuo Feedwater oumo and one Motor Driven Auri//arv Feedwater oumo are OOS. Rods are in auto. Tumover The olant is to maintained at the current condtions. [2FWF'P23Bf and f2FWS-P241. are OOS. Event No. Malf. No. Event Event ! Type
- Description 1
CL NH Main Feed Reg Valve oscillation in Auto requiring manual control , q 2 N/A R-RO Power reduction toless than 70% 0/SRO 3 MAL I N-44 fails high; rods insert in auto at 72 spm. One Bank D rod does not move. NIS3 RO/SRO Tech Spec entry. 4 # ' CR 8A RO/SRO 5 MAL C 2RCS-P218 #1 Seal Failure RCP1B RO/SRO 6 MAL M ATWS - FR-S.1 PPL1A1B R0/P0/ SRO 7 MAL M Small Break LOCA (small enough to allow Si termination) RCS2B RO/P0/ SRO 8 CLF C Motor Driven AFW pumps fail to start automatically, but can be manually started. P23A,P22 P0/SRO Steam Driven AFW pump trips upon start.
* (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor n
%J NUREG-1021 1 of 2 Interim Rev. 8, January 1997
4 Scenario #4 summary description. Unit 2 is at 75% power, steady state conditions. A problem with the 'C' MFRV will cause the crew to commence a power reduction in accordance with normal operating procedures. After a 5% power reduction, Power Range detector N-44 will fail high resulting in a rod insertion at 72 steps per minute. Pre-loaded in will be the failure of one Bank D rod (F6) to move. These failures are both Tech Spec entry conditions. This will be followed by the failure of the #1 seal on the "B" Reactor Coolant pump. A failure of both the automatic and manual Reactor Trips will occur resulting in the crew entering FR-S.1, Response to Nuclear Power Generation, ATWS. The failure of the #1 seal will result in a Small Break LOCA, which will result in a Safety injection. A Motor Driven AFW pump will fail to automatically start, but can be manually started. The steam driven AFW pump will trip upon start. The scenario will be terminated when the crew stabilizes the plant in accordance with ES-1.1, Si Termination. l 1 (#v j 2 of 2
4 Beaver Valley Power Station Unit 1/2 1/2OM-48.1.C CONDUCT OF OPERATIONS Issue 4 Revision 3 ORGANIZATIONAL AND RESPONSIBILITIES OF THE OPERATIONS GROUP Page C 7 of 28 SHIFT TURNOVER AND RELIEF Figure 48.1.C-2, Assistant Nuclear Shift Supervisor Shift Tumover Checklist Record Type A9.34tT
- Assistant Nuclear Shift Supermser .0VPS Unit No.
SHIFT TURNOVER CHECKLIST 0000 1848 2400
- 1. Oncoming and offgoing ANSS conduct a review of the control boards observing evolutions la progress, O O O unusual equipment or systems status and any unusual alarms or indications or status lighti
- 2. Rewsw premous shift narrauwe legs. (oncoming) O O O
- 3. Discuss any identified trends that require special attention. O O O
- d. Discuss any ternporary fogs, parameter trending or tempurary pax:edures in effect. O O O
- 5. Review MSPs. OSTs BVTs, PMPs (or other procedures affecting control room indications)in progress or 0 0 0 scheduled (oncoming).
- 6. Discuss any gas or liquid discharges in progress, o O O
- 7. Ust on reverse any Technical Speelficaton items in effect (by offgoing). Review list (oncoming). O O O
- 8. Vert 4 normal shift complement and emergency squad requirements are met (oncoming). O O O
- 9. Rev6ew the Clearance Program for posted and signed on clearances. O O O
- 10. Revtew the current Equipment OOS computer tracidng log printout (oncoming). O o a
- 11. Review the ESF Mimic Print for out of normal condsbons (oncoming). O O O
- 12. Discuss status of procedures in progress, being tumed over. 0 0 C (j 13.
- a. Circle the priority train 18 N/A for all modes other than A or B A or B A or B Modes 5 and 8
- b. Vertfy Normat and emergency power to priority train il/A for alt modes other than N E NE NE Modes 5 and g OO OO OO
- 14. The Nuclear Control Operators narratrve log; S14, 5, 6; or the NOMS Narrative log (dependent on which O O O is in use), has been reviewed to assure att significant items have been listed with adequale description.
- 15. Oncoming ANSS. log five (5) qualified fire brigade members in the ANSS tog; S.16.17,18. If in use. O O O
- 16. The offgoing ANSS signature cartrRes that their narrative log entries and the tour log entries made on a O O their shift are accurate, clear, concise and complete and that they have been property rulleved.
- 17. The offgoing ANSS prints out current copies of the Equipment OOS computer t-ackJng tog and distributes a o O to each watch station.
1 (Offgoing) (Oncoming)
)
1 (Signature) Date/ Time (Signature) Date/ Time (Signature) Date/Teme (Signature) . Date/Tlme (Signature) Date/ Time (Signature) Date/ Time it. The oncoming ANSS has reviewed the approved Control Room copy of the OST schedule. (Unit 2 LE.R 90403) (Signature) (signature) (Signature) n (Example . FRONT) FOR TRALNINIG USE ONLY l
Beaver Valley Power Station Unit 1/2 1/20M-48.1.C CONDUCT OF OPERATIONS issue 4 Revision 3
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ORGANIZATIONAL AND RESPONSIBILITIES OF THE OPS. GROUP Page C8 OF 30 ( t
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SHIFT TURNOVER AND RELIEF TECH SPEC ACTION ITEMS IN EFFECT (Soecial Surveillence Belo_w) _ Component / T. S. No. Date/ Time Date/ rime Date/ Time System Applied Due Complete
- 1) 2FWE*P23B 3.7.1.2.c Today -6 hrs ago 66 hours from now
- 2) 2FWS-P24 INFO
(~' REMARKS: 00-08
- l. Pump bearing replacement in progress. 2FWE*P22 aligned to 'B' header with 2FWE*36
!( shut and 2FWE* 102 open.
- 2. Info only - maintenance on speed increaser REMARKS: 08-16 REMARKS: 16-24 (EXAMPLE)
FIGURE NO. 48.1.C-2
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- g Figure 48.1 C-2, Assistant Nuclear Shift Supervisor Turnover Checklist I~
e'T , DUQUESNE LludOMPANY , Nuclear Power Division - Training Administrative Manual ~ t i 8-98-4 (iii)REVI ,
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t RCS boron - 983 PPM, CBD = 190 steps. Reactor power @ 75 % INITIAL CONDITIONS IC 12 VOND MARKINGS i STICKERS ADDITIONAL LINEUP CHANGES - 2FWE*36 shut 2FWS-P24 OOS - Pull-to-Lock Red Danger Tag Red Danger Tag 2FWE*102 open - 2FWE*P23B OOS - Pull-to-Lock Red Danger Tag 2FWE*38 shut 2FWS-MOV152 - De-energized DATE/ TIME T/S# AND TIME LIMIT EOUIPMENT STATUS i MARK j Today - 6 hours ago _ 3.7.1.2.c - 72 hour time limit 2FWE*P23B . 2FWE*P22 aligned to 'B' header . 2FWE*36 shut; 2FWE*102 open l 2FWS-P24 INFO SHIFT TURNOVER INFORMATION i
- 1. Crew is maintain stable current plant conditions. ;
- 2. 2FWE*P23B OOS for pump bearing replacement. Expected to be returned in 18 hours. 2FWE*P22 aligned to 'B' header.
- 3. 2FWS-P24 OOS for speed increaser maintenance.
- 4. CCP System - LCV's controllers are disconnected on VB'C'. Valves are controlled in auto from the process racks. DCV's ar *
" hunting" and possible valves leakage.
SCENARIO SUPPORT MATERIAL OM 1/2.48.1 Figure C-2 (ANSS Turnover Checklist) : INSTRUCTIONAL METHODS NOTES There shall be no direct intervention or assistance by the simulator instructor. Terminate the drill when directed by the exam team. l i I
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Nuclear Power Division Training Administrative Manual
- DRILL 8-98-4 REV 1 PAGE1 l PLANT STATUS OR RESPONSE l OBJECTIVE l EXPECTED STUDENT RESPONSE l l INSTRUCTIONAL GUIDELINES Initialize the simulator at IC-12 Reactor plant at 75% power, Equilibrium conditions, MOL,983 ppm boron; Bank D at 190 steps.
Insert:
******************************** Prevent Automatic and Manual ,
MAL PPLIA ACT,2,0,0,D Reactor Trip , MAL PPL1B ACT,2,0,0,D [ MAL PPL7A ACT,6,0,0,D Prevent Motor Driven AFW pumps MAL AFW3A ACT,5440,0,0,0,D from Automatically starting, but , pumps can be manually started. Steam Driven AFW pump trips on start. FILE LRTM4IC Aligns CCP system LCV's and DCV's
******************************** to match plant configuration ;
Insert: LOA HIV71 1,0,D
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2FWE*P23B OOS; discharge valve LOA ARV3 0,0,0,D shut VLV CFW271,0,D 2FWS-P24 OOS VLV CFW451,0,D 2FWS-MOV152 de-energized shut LOA AFW10,0,0,D 2FWE*P22 aligned to 'B' header LOA AFW131,0,0,D 2FWE-36 shut; 2FWE-102 open r
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(3 DUQUESNE Lite. dOMPANY Nuclecr Power Division Training Administrative Manual DRILL 8-98-4 REV 1 PAGE2 OBJECTIVE l EXPECTED STUDENT RESPONSE l l INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l After PCS startup, insert: . ANACK ANRSET FILE STUFFON FRZ Assign shift positions: NSS Simulator Frozen until after shift-
-ANSS turnover unless it needs to be on RO momentarily for an alignment change.
PO i STA Oncoming operators should complete the Conduct shin turnover with oncoming required checklists and carry out a formal operators. shift turnover. When the shift turnover is complete, Simulator running. Crew assumes control of the unit. place the simulator to RUN and , commence the drill. e******************************* i EVENT #1 - After approx. 2 min., insert Main Feedwater Regulating Valve Oscillation ,
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.DUQUESNE L u OMPANY ,
Nuclear Power Division Training Administrative Manual DRILL 8-98-4 REV 1 ~ PAGE 3 OBJECTIVE l EXPEC1ED STUDENT RESPONSE l l INSTRUCTIONAL GUIDELINES - l PLANT STATUS OR RESPONSE l PO notices main feed reg valve oscillations Insert: .
******************************** and informs ANSS
~ CNH CFW14 3,50,120,0,D 2FWS*FCV498 begins oscillating and could cause deviation alarms or
******************************** possible trip if not manually controlled MFRV position and feed flow stabilize ANSS directs PO to take manual control ofC MFRV and attempt to stabilize C SG in manual control.
feed and level. ANSS directs I&C to investigate apparent problem with C SG automatic MRFV control. NSS/ANSS should contact GMNO with As 1&C Tech., contact the ANSS to plant status informatica. inform him that the MFRV has I/P problems with the feedback linkage. It is bent and cracked. Strongly suggest removing valve from senice. ANSS directs operators to commence a
. If contacted as UOM, recommend plant load reduction, informs system and NSS of shutdown (or concur with NSS/ANSS the load reduction and the potential for a recommendation if they decide to reactor / turbine trip.
shutdown). Reactor power and turbine load are ANSS directs crew to commence a Load EVENT #2 decrease using 20M 52.4.B l decreasing. f
DUQUESNE Llo OMPANY ) , Nuclear Power Division Training Administrative Manual DRILL 8-98-4 REV : PAGE4 l PLANT STATUS OR RESPONSE l OBJECTIVE l EXPECTED STUDENT RESPONSE l l INSTRUCTIONAL GUIDELINES ANSS directs PO to set desired load rate POWER REDUCTION , and load on EHC Control Panel PO depresses GO pushbutton on EHC panel to begin raisingload PO monitors main generator for abnormal if requested, insert one of the fbliowing hydrogen gas temperatures commands: LOA CFW381,0,D 2RVS-P21 A aux lube oil pump LOA CFW391,0,D 2RVS-P21B aux lube oil pump RO maintains primary plant parameters PO maintains generator parameters within the limits of the Calculated Capability Curve (Fig. 52-5) and maintains power factor l EVENT 3 & 4 After the 5% power reduction, ' N44 failure with one bank'D roa failing to move. , 4
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Nuclear Power Division Training Administrative Manual DRILL 8-98-4 REV 1 PAGE 5 l INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l OBJECTIVE 'l EXPECTED STUDENT RESPONSE l Insen: , e............................... MAL CRF8A ACT,F6,1,0,0,D N44 fails high. On auto rod insertion due to failure, Control Bank D rod F6 MAL NIS3D ACT,200,0,0,0,D fails to move.
..s.............e...............
Power range Channel N44 indicates off scale high A4-4F NIS power range comparator deviation. A4-4G NIS power range neutron flux rate high. A4-4H NIS power range [ high setpoint overpower rod stop Crew notes alarms and indications. [ block rod W/D. A4-5G NIS power range high SP neutron flux high. Rods stepping in as a result of Channel Crew refers to AOP-2.1.3 "RCCA Control Monitor crew performance during N44 failure. Bank Inappropriate Continuous , implementation of AOP-2.1.3. Movement" and performs steps. . Crew recognizes no turbine runback exists. RO places rod control group selector ! NOTE: if crew addresses rod F6 first, Rod motion stops. switch in " MANUAL" actions of AOP 2.1.8 are listed after the actions of AOP 2.2.1C 4
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.DUQUESNE LIG COMPANY Nuclear Power Division Training Administrative Manual DRILL 8-98-4 REV 1 PAGE6 OBJECTIVE l EXPECitD STUDENT RESPONSE l l INSTRUCTIONAL GUIDELINES ' l PLANT STATUS OR RESPONSE l Crew! recognizes failure of Channel N44.
. Monitor crew during performance of .
ANS3 refers to AOP-2.2.lc " Nuclear . LAOP-2.2.lC to remove power range Instyumentation Malfunction" for NI Channel N44 from service. Ch:innel N44. ANSS directs operator to perform steps of AOP-2.2.lC to remove power range Channel N44 from service. N44 control power fuses (Drawer A) Crew performs AOP-2.2.1C. removed. Rod stop bypass switch to N44 position. Upper section comparator defeat switch to N44 position. Lower section comparator defeat switch to N44 position RO/PO removes control power fuses from N-44 RO verifies Rod Controlin Manual PO verifies Bypass Feed Reg valves in Manual RO/PO bypasses the rod stop for N-44 ANSS determines if QPTR requirements are met 1 l % s e
DUQUESNELlu. OCOMPANY f) v , Nuclear Power Division Training Administrative Manual DRILL 8-98-4 REV I PAGE7 INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE - l OBJECTIVE l EXPECTED STUDENT RESPONSE - l l RO/PO turns Comparator Channel Defeat Switch to N-44 ; N-44 should not be selected RO ensures NR-45 selected to monitor operable channels ANSS refers to Tech Spec 3.2.1 for axial flux and shows intent to comply ANSS refers to Tech. Spec. 3.3.1.1, identifies one hour action statement ' requirements and shows intent to comply. i ANSS contact I&C to investigate cause for NIS Channel N44 failure. Rod Inoperability AOP; Part B is for ANSS refers to AOP 2.1.8 for failure of Failure of Rod to move. rod to move ANSS directs crew to stop load changes Plant conditions in flux because of N- 7 or borations/ dilutions ifin progress 44 failure
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RO verifies Rod Controlin Manual , ANSS directs crew to adjust turbine load Plant bonditions in flux because of N-or borate / dilute as necessary to restore 44 failure equilibrium conditions i 4
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DUQUESNE LluidOMPANY .V- ~ Nuclear Power Division Training Administrative Manual
' DRILL 8-98-4 REV 1 PAGE 8 OBJECTlvE l EXPECTED STUDENT RESPONSE l l INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l ANSS requests I&C assistance in determining if rod is untrippable per TS 3.1.3.1.a 20ST-49.1 ANSS directs a Shutdown margin calculation be performed per TS 3.1.1.1 Continue with scenario and next event after completion of AOP-2.2.1,2.1.8, T.S. 3.3.1.1 and 3.2.1 are referenced and I&C contacted.
EVENT #5 Insert:
******************************** 2RCS-P21B Number One seal failure.
MAL RCPIB ACT,100,0,0,0,D RO notes alarms and indications, informs Due to rapidly degrading RCP RCP seal trouble alarm A2-4D (seal ANSS of RCP seal problems, refers to parameters, crew may attempt a manual leakoff flow high) and/or A2-4E (RCP ARP(s) as necessary. reactor trip prior to the low loop flow trouble). , auto trip signal.
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Crew determines the 2RCS-P21B #1 seal leakoff flow is >6 gpm ANSS directs the operator to trip the ATWS pre-loaded Reactor 9 4 .
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' DUQUESNE Ll6[, OMPANY ,
Nucle:r Power Division - Training Administrative Manual DRILL 8-98-4 REV 1 PAGE9 l PLANT STATUS OR RESPONSE l OBJECTIVE l EXPECTED STUDENT RESPONSE l l INSTRUCTIONAL GUIDELINES ANSS directs the operator to shutdown h It is expected the RO will not shutdown the RCP with the reactor 2RCS-P21B still critical ANSS directs the RO to close 2CHS*MOV303B within 3-5 minutes of ' securing 2RCS-P21B 2-3 minutes after requested, to allow for opening of the Reactor Trip Breakers locally, Insert: MAL PPL2A ACT,0,0,D MAL PPL2B ACT,0,0,D Manual Reactor Trip. RO notes a reactor trip has not occurred ATWS. ~ and attempts to trip the reactor, informs First Out: A5-5H ANSS of ATWS condition. RCS pressure drops, containment pressure and temperature rise. Operators commence immediate actions of Steps 1 - 5 of FR-S.I are immediate E-0 and FR-S.1; ANSS refers to E-0 and , actions. makes transition to FR-S.I. Turbine tripped, rods inserting. Crew manually trips the turbine and uses ; CRITICAL TASK - Crew inserts ! auto or manual rod control to insert rods. negative reactivity into the core by inserting RCCAs before completing the immediate actions steps of FR-S.1.
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-t Nuclear Power Division Training Administrative Manual DRILL 8-98-4 REV 1 PAGE 10 '
l PLANT STATUS OR RESPONSE l OBJECTIVE l EXPEC1ED STUDENT RESPONSE l l INSTRUCTIONAL GUIDELINES Crew sounds standby alarm, announces j Unit 2 reactor trip without scram. Crew dispatches an operator to locally trip reactor. , NSS evaluates EPP, declares a Site Area It is not expected that that the ANSS Emergency due to ATWS/FR-S.1 entry , will classify the event at this time (3 (TAB 2.3) within 15 minutes of first out man crew) annunciator, informs crew, provides AA t with notification form. Throttle, governor, reheat stop, and PO verifies turbine trip. interceptor valves all closed. Steam dump bypass interlock ' selector PO closes condenser steam dumps. switches in off. MSR steam supply block valves ' PO ensures reheat steam i' solation. closed. Reheat controller reset , ,
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Immediate actions complete. pushbutton depressed. . 2FWE*P23B OOS, P23A not running PO verifies AFW status. Manually starts 2 MSS *SOV105A-F open. 2FWE-P23 A and dispatches operator to 2FWE*HCV100A-F open. investigate trip of 2FWE-P22 2FWE-P22 tripped
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- Training Administrative Manual L DRILL 8-98-4 ' REV 1 PAGE11 l PLANT STATUS OR RESPONSE - l OBJECTIVE l EXPEUitD STUDENT RESPONSE l- .l . INSTRUCTIONAL GUIDELINES HHS1 pump (s) running. Crew initiates emergency boration.
1CHS*MOV350 open.
- Boric acid pump started.
Emergency boration flow indicated. 2CHS*FCV122 opened, > 40 gpm charging flow indicated. PRZR pressure < 2335 psig. RO ch-cks PRZR pressure less than 2335 psig. No SI annunciator or SI signal A12- Crew checks SI signal status ID lit. < 2-3 minutes after requested, insert Reactor trip breakers opened. RO informs ANSS that the reactor - All control rods fully inserted. tripped. previous commands and then report - RTBs manually opened. PO checks SG levels, verifies AFW flow is SG levels < 5% NR. greater than 700 gpm. . PO controls feed ' flow to maintain 5 - 50% narrow range level.
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RO ve'rifies dilution paths isolated. 2CHS*FCVIi3B closed. 2CHS*FCVI14A closed. 2CHS*FCVI14B closed. RO monitors RCS for uncontrolled cooldown. Y e __.m_m,m.m.__. _ _ _..__u.__ -
._ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ . _ _ _ _ _ - _ .___.____ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ ______ _ m __m
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- Nuclear Power Disision Training Administrative Manual
. DRILL 8-98-4 REV 1 PAGE 12 OBJECTIVE l EXPECTED STUDENT RESPONSE l I 'STRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l RO monitors RCS for uncontrolled cooldown. Uncontrolled cooldown not in ANSS goes to Step 16 ofFR-S.I. progress. PR NIs less than 5%. RO verifies reactor suberitical. IR NIs neg SUR.
' After the crew returns to E-0 EVENT #5 Insert: ******************************** 300 gpm LOCA on 'B' loop due to MAL RCS2B ACT,300,0,0,0,D seal failure ANSS makes transition from FR-S.1 back to E-0 and informs control room to perform E-0 immediate actions.
RO verifies reactor trip. Steps 1 - 7 of E-0 are immediate , Turbine trip due to reactor trip alarm , actions. AS-6D lit. Rod bottom lights lit. Neutron flux dropping. RO sounds standby alarm, announces reactor trip. i
DUQUESNE Llu OMPANY Nuclear Power Division Training Administrative Manual [t DRILL 8-98-4 REV 1 PAGE 13 . INSTRUCTIONAL GUIDELINES l PLANT STATUS ORRESPONSE l OBJECTIVE -l EXPECTED STUDENT RESPONSE l l J NSS continues EPP evaluation. t i Throttle or governor valves closed, PO verifies turbine trip. ! t reheat stops or interceptors closed. MSR steam supply block valves PO ensures reheat steam isolation.
.1 closed.
Reheat controller reset pushbutton depressed. Main generator output breakers open. PO verifies generator trip. Exciter circuit breaker open. 2AE and 2DF busses energized. PO verifies power to AC emergency . busses. RO checks if SI has actuated, identifies Any SI annunciator. Si actuation status light A12-ID lit. both trains failed to actuate and manually i Both trains of SI manually initiated. initiates both trains of SL l Both EDGs mnning. PO verifies EDGs running. . Immediate actions complete. . e 2FWE*P23B OOS, P23 A not running ~ PO verifies AFW status. Manually starts CRITICAL TASK - Crew establishes 2FWE-P23A and dispatches operator to [ the minimum required AFW flow rate to 2 MSS *SOV105A-F open. l 2FWE*HCV100A-F open. investigate trip of 2FWE-P22 the SGs before transition out of E-0 , unless transition is to FR-H.1, in which 2FWE-P22 tripped case flow is established prior to trip of [ i the RCPS , i e i
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DUQUESNE L1 OMPANY Nuclear Power Division
- Training Administrative Manual -
DRILL 8-P8-4 REV 1 PAGE 14 l INSTRUCTIONAL GUIDELINES l -PLANT STATUS OR RESPONSE l OBJECTIVE l EXPECTED STUDENT RESPONSE l Two service water pumps running. RO verifies service water pumps in Service water header pressure 55- 124 service. psig. HHSI pumps running. RO verifies SI status. HHSI flowindicated. LHSI pumps running. SI valve alignment - all indicating lights with red SIS marks lit. CIA actuated, all indicating lights with RO/PO verify CIA. orange CIA marks LIT. If requested to restore 2FWE-P22, All indicating lights with green marks RO/PO verify FWI. insert: FW1 marks lit. MAL AFW3A CLR LOA AFW22 0,0,D CNMT pressure < 3 psig. RO/PO check if main steamline isolation is Steamline pressur~e > 500 psig. required. Steamline pressure rate < 100 psig in , 50 seconds. CIB alarm not lit. RO checks CIB/ spray status. Containment pressure < 8 psig. 4
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n ' j-v s ( (- DUQUESNE LI6an') COMPANY .i Nuclear Power Division , Training Administrative Manual DRILL 8-98-4 REV I PAGE 15 l INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l OBJECTIVE l EXPECTED STUDENT RESPONSE l ; Filtered water valve 2CCS-AOV118 PO establishes filtered water cooling to the ! opened. station air compressors. , One station air compressor running. Two CCP pumps running. RO/PO verify CCP in service. ; 7 I SR channels aligned properly. RO verifies SR detector high voltage switches in normal. AFW flow > 365 gpm. PO verifies AFW flow greater than 365 gpm.
- Tavg trending to 547 F. RO verifies RCS Tavg stable at or ;
trending to 547 F. ANSS directs available personnel to perform emergency safety functions
- checklists.
Recirc spray pumps secured. RO checks recirc spray pump status. I i
DUQUESNE L1 OMPANY [) Nuclear Power Division ; Training Administrative Manual DRILL 8-98-4 REV I PAGE 16 1 ~l INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l OBJECTIVE l EXPECIED STUDENT RESPONSE l PORVs closed (not leaking). RO checks PRZR isolated. Spray valves closed. Safeties closed (PSMS data). PRT conditions normal: 2RCS*P21 A and C running. RO checks if RCPs should be stopped. RCS to SG D/P satisfactory. CCP flow normal. No SG pressure dropping Crew checks if any SGs are faulted. uncontrollably or completely depressurized. Secondary rad monitors consistent Crew checks if SG tubes are intact. with pre-event levels. CNMT radiation, pressure, and sump Crew checks containment conditions level rising. consistent with pre-event values. l ANSS makes transition from E-0 Step 27 to E-1 and informs crew. Control Room Rad Monitors not in Crew Checks Control room habitability high alarm RCS to Highest SG delta p > 145 psid RO/PO Check if RCPs should be stopped ; with HHSI flow or - No cooling water flow None mnning RO Checks Recirc Spray Pump Status i i s
O DUQUESNE Llw JOMPANY n - Nucle::r Power Division - Training Administrative Manual
.- DRILL 8-98-4 REV 1 PAGE 17 '
OBJECTIVE ~ l EXPECTED STUDENT RESPONSE l ,-l INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l RO Verifies both CNMT Hydrogen i Both analyzers on; amber light lit Analyzers running i PO Checks if any SGs are faulted No pressures dropping in an uncontrolled manner or none i completely depressurized No levels rising in an unexpected PO Checks intact SG levels manner and no rad monitor alarms PORVs closed RO Checks Przr PORVs and Motor Motor Operated Isolation valves Operated Isolation Valves energized and open ; Subcooling Crew Checks if SI Flow can be terminated , RCS Pressure stable or rising Adequate secondary heat sink . , Pressurizer level 4 ANSS makes transition from E-1 step 8 to ES-1.1 step 1 and informs crew t
-RO Isolates CNMT Vents and Drains 2CVS-P21 A&B PTL 2DAS-P204A&B stop system 2DGS-P21 A&B PTL .
RO Resets SI(Both Trains) RO Resets CIA and CIB (Both Trains)- . L P i e I
DUQUESNE Liu , COMPANY
- Nuclear Power Division Training Administrative Manual '
DRILL P-98-4 REV 1 PAGE 18. l PLANT STATUS OR RESPONSE l OBJECTIVE l EXPECTED STUDENT RESPONSE l
- l ' INSTRUCTIONAL GUIDELINES RO Stops ore HHSI pump Terminate Drill after crew secures 2nd HHSI pump in ES-1.1 Collect and review logs after allowing _ Operator logs should be clear, accurate and concise.
operators to complete them. Erase any vond markings associated with this drill. NOTE: The expected EPP declaration is a SITE AREA EMERGENCY on TAB 2.3, Failure of Reactor Protection. J t e e e 9 e a
/
Appendix D Scenario Outline Form ES-D-1 (lw) Facility: Beaver Vallev Power Station Unit 2 Scenario No.: 5 Op-Test No.: 2 LOT 2A Examiners: Operators: Objectives To evaluate the anolicants ability to use Normal. Abnormal. Emeraency and Alarm Resoonse orocedures tg resoond to a non-recenerative heat exchanaer coolina water orablem. a letdown oroblem. a stearn eenerator tube leak. a larae break LOCA coincident with a failure of safety iniection to automatically initiate. and a failure of automatic transfer 1g cold lea rerirculation. Initial CondtionT The unit is at 100% oower. steadv state condtions. Rods are in auto. The Startuo Feedwater oumo and one Motor Drivca AFW oumo are out of service. Tumover. The olant is at 100% oower. l2FWS-P241 and f2FWE*P23B1 are OOS. l I Event No. Malf. No. Event Event Type
- Description CLF C Non-regenerative heat exchanger TCV fails closed causing heatup of VCT and 1
CCP19 RO/SRO sealinjection l MAL ~C Steam Genemur Tube Leak greaterthe, Tech Spec LCO requiring 2 fy RCS4 RO/PO/ shutdown .A SRO _ ; l ~) 3 N/A R-RO N-PO/ Powerreduction to comply with Steam Generator Tube Leak AOP actions SRO 4 CLF I 2CHS-PT145 fails high, causing PCV145 to close andletdown to isolate. LDS7 RO/SRO I (Note the failure of the controlleris auto ormanual) l LOS10 5 MAL C Both Trains of Si fail to actuate PPL5A, RO/SRO PPL5B 6 MAL M Large Break LOCA i RCS3A RO/P0/ i SRO ! 7 CLF C- Main FeedReg Valves failopenin auto andmanual CFW PO/SRO l B Leak SIS 1 C .A" LHSI suction Leak and MOV8809A de-energized open, and 'A' LHSI pump VLV RO/SRO trips after 3 minutes SIS 75 g BST M Auto Transfer to Cold Leg Recirculation Failure PCS84-87 RO/SRO 1
* (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor (3
NUREG-1021 1 of 2 Interim Rev. 8, January 1997
Scenario #5 summary description. { The Unit is at 100% power when a failure of the Non-regenerative heat exchanger Temperature Control Valve occurs, resulting in a heatup of the VCT and charging and seal in}ection. Next, a Steam Generator Tube Leak will occur resulting in a plant shutdown, and Tech Spec entry. After a 5% power reduction, 2CHS- { i PCV145 will fait closed, isolating letdown, and requiring that Excess Letdown be placed into service. A Large Break LOCA will occur. Pre-loaded will be a failure of both trains of Safety injection to occur automatically. The Main feedwater ] Regulating Valves will fail open in both auto and manual. Also, a leak will develop at the suction of the Low Head Safety injection pump 2 SIS *P21 A and the pump will trip 3 minutes after starting. The suction valve to the pump will also be de-energized open. This sequence will also serve to help tower the RWST level, as there is a failure of the Automatic Transfer to Cold Leg Recirculation to occur. The scenario will be terminated after the crew manually initiates Cold Leg Recirc in accordance with ES-1.3, Transfer to Cold Leg Recirculation. ( I A 2 of 2 l
Beaver Valley Power Station Unit 112 1/2OM-48.1.C CONDUCT OF OPERATIONS lssue 4 Revision 3 [] C./ ORGANIZATIONAL AND RESPONSIBILITIES OF THE OPERATIONS GROUP Page C 7 of 28 SHIFT TURNOVER AND RELIEF Figure 481.C-2, Assistant Nuclear Shift Supervisor Shift Turnover Checklist Ruord Type A9.341T . Assistant Nuclear SNft Superwsor ,BVPS Unit No. SHIFT TURNOVER CitECKLIST 0800 1644 2400
- 1. Oncoming and offgoing ANSS conduct a rewew of the control boards observing evolubons in progress, O O O unusual equipment or systems status and any unusual alarms or indications or status lights.
- 2. Revier previous shift narrateve logs. (oncoming) O O O
- 3. Discuss ~ any identified trends that require spedal attention. O O O
- 4. Discuss any temporary logs, parameter trending or temporary procedures in effect. O O O
- 5. Review MSPs, OSTs, BVTs, PMPs (or other procedures affecung control room indications)in progress or O O O scheduled (oncoming).
- 6. Discuss any gas or liquid discharges in progress. O O O
- 7. List on reverse any Technical Spedficaton items in effect (by offgoing). Rwiew hst (oncorrung). O O O
- 8. Vertfy normal shift complMnent and emergency squad requirements are met (oncoming). O O O
- 9. Review the Clearance Program for posted and signed on dearances. O O O
- 10. Rev6ew the current Equipment 00S computer tracking tog prtntout (ona mingt 0 0 U t1. Review the ESF Mimic Print for out of normal conditions (oncoming O O O
- 12. Discuss status of procedures in progress, being turned owr. O O O C/ 13.
- a. Circle the priority trainto WA for att modes other than A or B A or B A or D Modes 5 and 6
- b. Vatify Normal and emergency power to priority train NA for all enodus other than N E ft E NE Modes 5 and 6 0 0 00 0 0 14, The Nudear Control Operators narrative log; SI-4, 5, S; or the NOMS Narrative log (dependent on which 0 0 0 is in use), has been reviewed to assure all significant items have been listed wnth adequate description.
- 15. Oncoming ANSS, tog five (5) qualified fire Mgade members in the ANSS log; S.16,17,18, if in use. O O U
- 16. The offgoing ANSS signature certifies that their narrauve log entries and the tour log entries made on O O O their shift are accurate, de t, concise aM complete and that they have been property relieved.
- 17. The offgoing ANSS prints out current cop 6es of the Equipment OOS computer traceang tog and distributes O O O to each watch station.
(Offgoing) (Oncoming) (Signature) Date/ Time (Signature) Date/ Time (Signature) Date/ Time ' (Signature) Date/ Time (Signature) Date/ Time (Signature) Date/ Time
- 18. The oncoming ANSS has reviewed the approved Control Room copy of the OST schedule. _
(Unit 2 (IR 90403) (Signature) (signature) (Signature) g
; ) (Example . rRONT)
Q) FOR TRALNING US'E ONLY . l 1
Beaver Valley Power Station Unit 1/2 1/20M-48.1.C CONDUCT OF OPERATIONS Issue 4 Revision 3 [D ORGANIZATIONAL AND RESPONSIBILITIES OF THE OPS. GROUP Page C8 OF 30 (J... SlilFTTURNOVER AND RELIEF TECH SPE_C_ ACTION ITEMS IN EFFECT (Special Surveillence Below) Component / T. S. No. Date/ rime Date/ Time Date/ rime System Applied Due Complete
- 1) 2FWE*P23B 3.7.1.2.c Today -6 hrs ago 66 hours from now
- 2) 2FWS-P24 INFO l
l l l l l l i
)
REMARKS: 00-08
- 1. Pump bearing replacement in progress. 2FWE*P22 aligned to 'B' header with 2FWE*36 l.()
shut and 2FWE*102 open.
- 2. Info only - maintenance on speed increaser REMARKS: 08-16 l
REMARKS: 16-24 (EXAMPLE) FIGURE NO. 48.1.C-2 U l 1 I Figure 48.1.C-2, Assistant Nuc! car Shitt Supervisor Turnover Checklist
DUQUESNE LIub.lOMPANY , Nuclear Power Division , Training Administrative Manual 8-98-5 (iii)REV1 RCS boron - 732 PPM, CBD = 227 steps. Reactor power @ 100 % INITIAL CONDITIONS IC 18 ' VOND MARKINGS STICKERS ADDITIONAL LINEUP CHANGES 2FWE*36 shut 2FWS-P24 OOS - Pull-to-Lock Red Danger Tag Red Danger Tag 2FWE*102 open 2FWE*P23B OOS - Pull-to-Lock Red Danger Tag 2FWE*38 shut 2FWS-MOV152 - De-en-rgized DATE/ TIME T/S# AND TIhm LIMIT EOUIPMENT STATUS MARK Today - 6 hours ago 3.7.1.2.c - 72 hour time limit 2FWE*P23B 2FWE*P22 aligned to 'B' header i 2FWE*36 shut; 2FWE*102 open 2FWS-P24 INFO SHIFT TURNOVER INFORMATION ,
- 1. Crew is maintain stable current plant conditions.
- 2. 2FWE*P23B OOS for pump bearing replacement. Expected to be retumed in 18 hours. 2FWE*P22 aligned to 'B' header.
- 3. 2FWS-P24 OOS for speed increaser maintenance.
- 4. CCP System - LCV's controllers are disconnected on VB'C'. Valves are controlled in auto from the pocess racks. DCV's ar
" hunting" and possible valves leakage. i SCENARIO SUPPORT MATERIAL OM 1/2.48.1 Figure C-2 (ANSS Turnover Checklist)
INSTRUCTIONAL METHODS NOTES There shall be no direct intervention or assistance by the simulator instructor. Terminate the drill when directed by the exam team.'
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U(~N DUQUESNE Liv (,.)OMPANY Nuclear Power Division () '
+
Training Administrative Manual DRILL 8-98-5 REV 1 PAGE1 INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l OBJECTIVE l EXPECTED STUDENT RESPONSE l l Insert INIT 18 Plant is at 100%' power, equilibrium RUN conditions. RCS Boron is 732 ppm, Control Bank D is at 227 steps. Insert: e...e************************* MAL PPL5A ACT,1,0,0,D Defeat Automatic SafetyInjection . MAL PPL5B ACT,1,0,0,D BST PCS84 2,0,D Prevent Automatic Transfer to Cold BST PCS85 2,0,D Leg Recirc BST PCS86 2,0,D BST PCS87 2,0,D LEAK SIS,1,1,5000,0,0,C,JPPLSIA Leak at suction of 2 SIS *P21 A with VLV SIS 75 suction valve de-energized open and 1,10,C,OSIP21 A.GT.0.1 pump tripping 3 minutes after starting. PMP SISI 2,180,C,OSIP21A.GT.0.1 , FILE LRTM4IC Aligns CCP system LCV's and DCV's to match plant configuration . i e 9 e
p [N % f DUQUESNELlub OMPANY )- , Nuclear Power Division Training Administrative Manual DRILL 8-98-5 REV 1 PAGE 2 OBJECTIVE l EXPECTED STUDENT RESPONSE l l INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l Insert; . VLV CFW271,0,D 2FWS-P24 OOS VLV CFW451,0,D 2FWS-MOV152 de-energized shut Insert; LOA IIIV71 1,0,D 2FWE*P23B OOS LOA AFW3 0,0,0,D 2FWE*38 shut LOA AFW10,0,0,D 2FWE*P22 aligned to 'B' header LOA AFW131,0,0,D 2FWE-36 shut; 2FWE-102 open Insert: VLV CFW341,0,C,JPPLFO Prevents auto closure of Main Feed reg VLV CFW361,0,C,JPPLFO valves on FWI. in auto or manual VLV CFW381,0,C,JPPLFO
....e...................... ..
After PCS startup, insert: ANACK ANRSET FILE STUFFON , FRZ , Assign shift positions: NSS Simulator Frozen until after shift ANSS turnover unless it needs to be on RO momentarily for an alignment change. PO STA 4
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,[.k} DUQUESNE LlujOMPANY -
Nuclear Power Division DRILL 198-5 REV 1 PAGE3 INS 7 k'3CTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l OBJECTIVE l EXPECTED STUDENT RESPONSE l l . Conduct shin turever with oncoming , Oncoming operators should complete the required checklists and carry out a formal i operators. shin turnover. t 9At9A************************* e When the shift turnover is complete, Simulator running. Crew assumes control of the unit. place the simulator to RUN and commence the drill. i esame*************************
- RO acknowledges alarm and takes manual EVENT #1 control of 2CCP-TCV144 .
Insert: i
.............................. 2CCP-TCV144 fails closed i CNH CCP19 2,100,0,0,D Letdown flowpath trouble alarm A2-3F RO adjusts TCV144 to restore temperature NRHX alarms clear within a few minutes of restoring manual control. (NRHX relief temperature high, T0136D; NRHX discharge pressure high, P0137D). I t
EVENT #2 l Insert: !
...y..************************ Steam Generator Tube Leak greater MAL RCS4A ACT,25,0,0,0,D than Tech Spec Limit requiring plant ; ...........*........********** shutdown 4
4 4 _ . . _ _ __.___.____..___m_______.__.__._____.___
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/"y O DUQUESNE Llt UOMPANY ; ,
Nuclear Power Division Training Administrative Manual DRILL 8-98-5 REV 1 PAGE4 OBJECTIVE l . EXPECTED STUDENT RESPONSE l l INSTRUCTIONAL GUIDELINES. l PLANT STATUS OR RESPONSE l 2 ARC-RQ100 (air ejector) and RO acknowledges alarms, informs ANSS. Set Bits = +10 for XMT RMSI and RMS96 2SSR-RQ100 (blowdown sample Insert: radiation monitor) response.
******************************** Charging flow rises to compensate, XMT RMS12,10,0,0,D VCT level gradually drops. ' XMT RMS96 2,10,0,0,D Blowdown sample radiation monitor ******************************** 2SSR-RQ100 rises through alert and SG blowdown automatically isolates high alarm values.
upon 2SSR-RQ100 high alarm Radiation monitor system trouble (A4-actuation. SA) and level high (A4-5C) alarms actuate. Crew refers to ARPs as necessary. - Crew monitors DRMS RM-Il console for affected radiation monitor channels. ANSS refers to AOP-2.6.4, crew performs necessary actions. Crew requests Chemistry support (leak rate and isotopic analysis). t 4 S
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.QL DUQUESNE LIus , COMPANY '
Nucie:r Power Division Training Administrative Manual DRILL 8-98 REV 1 PAGE5 l PLANT STATUS OR RESPONSE l OBJECTIVE . l EXPEUitD STUDENT RESPONSE l
'l INSTRUCTIONAL GUIDELINES Leak rate > 15agpd. Crew determines that leak rate requires a plant shutdown to Mode 3 4
25 gpm leak > T.S. limit. ANSS verifies compliance with T.S. Activity value pending Chemistry 3.4.6.2 and 3.7.1.4. reports. Monitors placed in service PO verifies main steamline radiation (2 MSS *SOV120 open). monitors available. 2 MSS *15 closed,2 MSS *16 and *17 Crew isolates TDAFW pump steam supply checked open. from A SG. Atmospheric dump valve Crew isolates flow from A SG. 2SVS*PCV101 A setpoint adjusted, , I valve closed. Crewisolates 2SVS-HCV104 from A SG 2SVS*27 closed. Crew determines appropriate SG Blowdown isolation valves blowdown flowpath ; 2SSR*A,OVI17A,B,C and 2BDG*AOV100Al,B1,Cl closed (automatic isolation due to high alarm , on 2SSR-RQ100). Crew verifies primary to secondary leakrate > 142 gpd, addresses oil / water separator operations.
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DUQUESNE LILE COMPANY ., Nuclear Power Division Training Administrative Manual DRILL 8-98-5 REV 1 PAGE6 INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l OBJECTIVE l EXPECTED STUDENT RESPONSE ' l _ l Crew requests Health Physics assistance. . l-r AOP-2.6.4 complete. Crew may transfer auxiliary steam to Unit I or aux. boilers. ANSS directs crew to commence a normal plant shutdown, refers to 20M-52.4.B (Load Following). Crew informs System Operator. Crew notifies Upper management / GMNO EVENT #3 - REACTOR POWER DECREASE 1 Crew commences power decrease in accordance with reactivity plan. + Continue reactor shutdown to - 95% Reactor at 95%. power. - RO inserts rods to lower reactor power to ' 95%. PO lowers turbine load using EH reference and setter and GO/ HOLD pushbuttons on EH control panel . t
['N DUQUESNE f' Lluk,]40MPANY \ Nuclear Power Division Training Administrative Manual DRILL 8-98-5 REV 1 PAGE7 OBJECTIVE l EXPECTED STUDENT RESPONSE ' l l INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l PO maintains S/G NR within alarm . After 5% power reduction . setpoints. EVENT #4 Insert:
****************************** 2CHS-PT145 fails high. RO acknowledges alarm and reviews board. Crew refers to ARP A2-3F,if XMT LDS71,0,0,0,D 2CHS-PCV145 fails closed in auto and necessary.
CNH LDS10 5,100,0,0,D manual Ann. A2-3F - Non Regen HX outlet RO informs ANSS that 2CHS*PCVl45 pressure high has failed shut . ANSS/ operator directs Aux Bldg. 2CHS*PCV145 failed closed operator to investigate status of 2CHS*PCV145. ANSS directs RO to secure charging and ; letdown ; RO closes any opened letdown orifice Letdown isolated , isolation valve: 2CHS*AOV200A, B , and/or C RO takes manual control of 2CHS-FCV122 and reduces charging flow to minimum to control PRZR level
DUQUESNE LlubOMPANY [ l /^ Nuc!:ar Power Division
. Training Administrative Manual DRILL 8-98-5 REV 1' PAGE8 OBJECTIVE l EXPECTED STUDENT RESPONSE l l INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l ANSS directs crew to initiate excess letdown IAW 20M-7.4.G RO/PO checks 2CCP-AOV170 and 105 open RO/PO checks 2CHS-HCV389 in the VCT position Only one valve needs to be opened RO/PO opens an RCS drain valve; 2RCS-MOV557A,557B, or 557C l
RO/PO opens 2CHS-MOV201 RO/PO monitors seal injection flows and seal leak-otTflows for RCPs RO/PO adjusts 2CHS-FCV137 to Pressurizerlevelis stabilized and returning to normal. establish excess letdown flow i Outlet temp <140F RO/PO monitors 2CHS-TIl39 and Outlet press <l35 psig 2CHS-PIl38 RO/PO monitors seal injection flow at 6-9
~
'8Pm per pump Previously completed RO/PO verifies / closes 2CHS- '
AOV200A.B,C and 2CHS-FCV122 RO/PO closes 2CHS-MOV289 l
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y . i DUQUESNE Llu OMPANY Nuclear Power Division Training Administrative Manual ; DRILL 8-98-5 REV 1 PAGE9 OBJECTIVE l EXPECTED STUDEF USPONSE l l INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l ANSS determines if total seal injection . flow is >28 gpm and references TS 3.5.4 ifrequired i ANSS evaluates the need for increased l surveillance of RCS activity and chemistry , and contacts Chemistry / Health Physics as appropriate ANSS directs I&C to investigate 2CHS*PCV145 automatic control problem. EVENT #5 RO informs ANSS of a trip and first out DBA LOCA on RCS loop A. RCS Insert: annunciator.
****************************** pressure, PRZR level drop rapidly.
MAL RCS3A ACT,0,0,D CNMT parameters degrade rapidly. Reactor trip, auto SI fails to activate. First Out: PRZR pressure low, A5-4H, MONV LQS:100A
****************************** PO488D.
Monitor RWST level for Transfer to Recirc setpoint. , , RO and PO commence immediate actions of E-0, ANSS references E-0 to verify immediate actions. 4
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_----_7-t f~s Q (~) Q DUQUESNE Lluw.20MPANY
- ' Nuclear Power Division Training Administrative Manual DRILL 8-98-5 REV 1 PAGE 10 OBJECTIVE l EXPECTED STUDENT RESPONSE l .
l INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l
' RO verifies reactor trip. , . Steps 1 - 7 of E-0 are immediate Turbine trip due.to reactor trip alarm i actions. A5-6D.
Rod bottom lights lit. Neutron flux dropping. RO/PO sounds standby alarm, announces Unit 2 reactor trip and SI. NSS evaluates EPP and declares ALERT It is not expected that the ANSS will due to Loss of RCS Barrier (TAB 1.2). classify the event at this time (3 man crew) PO verifies turbine trip. Throttle or governor valves closed. Reheat stops or interceptors closed. MSR steam supply block valves PO ensures reheat steam isolation. closed. Reheat controller reset pushbutton depressed. PO verifies generator trip. Main generator output breakers and Exciter circuit breakers open. , PO verifies powdr to AC emergency 2AE and 2DF busses energized. busses. b e
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DUQUESNELlu(. dOMPANY - Nuclear Power Division , Training Administrative Manual DRILL 8-98-5 REV 1 PAGEII OBJECTIVE l EXPECieD STUDENT RESPONSE l l INSTRUCTIONAL GUIDELINES - l PLANT STATUS OR RESPONSE l EVENT #5 . RO checks if SI is actuated. Auto SI fails to actuate. SI has not actuated. - Crew checksilSIis required. RCS
- CRITICAL TASK - Crew manually RCS pressure < 1855 psig. <
CNMT pressure > 1.5 psig. pressure < 1855 psig. CNMT pressure > actuates at least one train of SIS 1.5 psig. Crew determines SI is required. actuated safeguards before transition to : any ORP. RO manually actuates SI. Immediate actions complete. SI actuated. PO verifies EDGs mnning. Crew should implement adverse EDGs running. containment values when CNMT pressure > 1.5 psig. 2FWE*P23 A running (2FWE*P23B PO verifies AFW status. OOS). 2 MSS *SOV105A-F open. 2FWE*HCV100A-F open. RO verifies service water systemin Two service water pumps running (one service. per train). Service water header pressure 55-124 psig. 4 I
e m ,' . p f. O DUQUESNE LIG COMPANY .. Nuclear Power Division Training Administrative Manual DRILL 8-98-5 REV 1 ' PAGE 12 OBJECTIVE l EXPECitD STUDENT RESPONSE l l INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l HHSI pumps ninning. RO verifies SI status. HHSI flow indicated. i SI valve alignment - allindicating lights with red SIS marks lit. RO identifies suction valve de-energized EVENT #6 "A" LHSI pump trips 3 minutes after
~and 2 SIS *P21 A trip (time dependent) and "A" LHSI pump suction leak (5000 starting.
2 SIS *MOV8809A deenergized. notifies ANSS. 4 gpm) occurs at valve. 2 SIS *MOV8809A deenergized and "A" s LHSI pump (2 SIS *P21 A) trips 3 minutes after starting. ANSS dispatches operator to investigate Safeguards sump alarm lit. cause of Safeguards Sump Annunciator. CIA actuated, all indicating lights with RO/PO verify CIA. orange CIA marks LIT. RO/PO verify FWL. PO notes failure of i All indicating lights with green marks l 2FWS-FCV478,488,498 and informs lit.. Pre-loaded failure of Main Feed ANSS. PO may close 2FWS-- Reg Valves ' MOV154A,B,C as backup isolation (not required). PO should re verify 2FWS-HYV157A,B,C closed , i RO/PO check MSLI is required. [ All indicating lights with yellow marks lit. t
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p ,. DUQUESNE LlubMOMPANY - Nuclear Power Division Training Administrative Manual DRILL 8-98-5 REV 1 PAGE 13 OBJECTIVE l EXPECTED STUDENT RESPONSE l l INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l RO verifies CIB and containment spray CIB and containment spray required. status. Verify CTMT spray initiated. Verify all indicating lights with blue marks lit. Stop all RCPs. RCPs secured. PO establishes domestic water cooling to 2CCS-AOV118 opened. One station station air compressors.
- air compressor running.
RO!PO verify CCP in service. CCP pumps stopped due to CIB. RO verifies SR detector high voltage SR channels aligned properly. switches in normal PO verifies AFW flow greater than 365 Total AFW flow > 365 gpm. gpm. RO verifies RCS Tavg stable at or ,
, Plant cooling down due to DBA, RNO trending to 547 F.
actions verified. ANSS directs personnelto perform emergency safety function checklists. 9 _____m._. _ ____ _ -______ _
7}.
\, [ ^ (~~\
.Q -
DUQUESNE LIub< COMPANY Nucle:r Power Division ~! Training Administrative Manual 4 . DRILL 8-98-5 REV 1 PAGE14 OBJECTIVE EXPECTED STUDENT RESPONSE l l l PLANT STATUS OR RESPONSE l l l INSTRUCTIONAL GUIDELINES - Recirc spray pumps start after RO checks recirc spray pump status. appropriate time delay. , PORVs closed (not leaking). RO checks PRZR isolated. Spray valve closed. Safeties closed (PSMS data). PRT conditions normal. RCPs secured. RO checks RCP status. Crew checks if any SGs are faulted. No faulted SGs. Secondary rad monitors consistent Crew checks if SG tubes are intact. with pre-event levels. CNMT pressure rising. Crew checks containment conditions consistent with pre-event values. , CNMT sump level rising. CNMT radiation rising. ANSS makes transition from -0 to E-I, and informs crew. STA begins monitoring status trees.
cv O' DUQUESNE LIO.m20MPANY - NucleuPower Division Training Administrative Manual DRILL 8-98-5 REV 1 PAGE 15 OBJECTIVE l EXPEC1ED STUDENT RESPONSE l l INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE ! STA informs ANSS of a red path on Note: If FR-P.I is not entered . integrity. immediately, follow E-1 actions. ANSS informs crew he is making ~ transition to FR-P.I. L RO checks RCS pressure > 185 psig and RCS pressure < 185 psig. LHSI flow > 1050 gpm. LHSI flow > 1050 gpm. ANSS returns to procedure and step in Note: Crew may have to perform effect (E-1). FR-Z.1 if CNMT pressure is more than
' 8 psig. Monitor crew implementation.
PO checks control room habitability.
- E-1 actions. CIB has occurred.
All control room britled air discharge PO verifies CREBAPS actuated. , Report Unit I actuation satisfactory when requested. lights arelit. 2HVC* MOD 201 A,B,C,D closed. RO checks if RCPs should be stopped. RCPs secured. *
. i RO checks recirc spray pump status.
All pumps running. After 10 5 minute time delay ! RO verifies H2 analyzers mnning. CNMT sample amberlights lit. t
~Q
~V f')
- DUQUESNE LIO.._.,40MPANY p
1V , Nuclear Power Division Training Administrative Manual
-DRILL 8-98-5 REV 1 'PAGE 16 OBJECTIVE l EXPECTED STUDENT RESPONSE l l- INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l No faulted SGs. PO checks if SGs are faulted.'
s PO checks intact SG levels and controls feed flow to controllevels.- - i Power available to block valves. RO checks Pzr PORV and block valves. PORVs closed (not leaking). 1 PORV block valves open. _ No subcooling. Crew checks if SI flow can be terminated. No SG levels rising in an uncontrolled Crew checks if SG tubes are intact. . manner. Secondary radiation levels normal, ANSS checks if CNMT spray should be Continuous action step. Quench and recirc spray pumps running. CTMT pressure less than -2 stopped.
- Note
- May not be performed at this j CNMT pressure < -2 psig.
time if CNMT pressure > -2 psig. psig.~ Reset CIB. i CIB reset RWST level greater than 460 in. . Check RWST level. , No faulted SG. Check for faulted SG. If containment pressure > -5 psig, CNMT pressure'> -5 psig. plant operators directed to cycle RSS Monitor CNMT pressure. pumps. f
. ,/3 ;
f')
% ~ . DUQUESNE LludOMPANY V ~ ,'
- Nuclear Power Division Training Administrative Manual DRILL 8-98-5 REV 1 .PAGE 17 INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l - OBJECTIVE l - EXPECTED STUDENT RESPONSE - l l
Note: When RWST level decreases to .
. less than 460", ANSS should transition to ES-1.3.
L 2CVS*P21 A,B PTL. RO isolates CNMT vents and drains, . 2DAS-P204A,B stop. resets SI, CIA. 2DGS-P21 A,B PTL. SI reset. CIA reset. i RCS pressure < 185 psig. RO checks ifLHSI pumps should be LHSI pumps required. stopped. 2AE and 2DF busses energized by PO checks if EDGs should be stopped. Note: RCS pressure and SG pressure offsite power. j stabilize eventually. Monitor crew performance in E-1 until conditions satisfy continuation in procedure. l EDGs secured. PO stops unloaded EDGs. Crew verifies cold leg recirc capability. I j Power available, except 2 SIS-P21 A , P Power available to valves in Operators perform Attachment A-0.6. Attachment A-0.6, except 2 SIS-P21 A 7 suction valve i !
DUQUESNE L1 OMPANY ~ Nuclear Power Division Training Administrative Manual DRILL 8-98-5 REV 1 PAGE 18 , INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l OBJECTIVE l EXPECTED STUDENT RESPONSE l l No unexpectedincrease. Crew checks Aux Building and safeguards radiation. Crew directs Chemistry and Rad Con to - obtain samples. o Crew starts additional plant equipment to assist in recovery. RCS pressure less than 185 psig. ANSS determines method of cooldown for . LHSI flow greater than 1050 gpm. long term plant recovery. RWST less than 460 inches. Crew verifies transfer to cold leg CRITICAL TASK - Crew transfers to recirculation when required. cold leg recirc and establishes ECCS ! recirc flow, before loss of coolant flow to the core. ANSS informs control room of transition to ES-l.3 for cold leg recirc. Preloaded failure of cold leg recirc to ANSS verifies cold leg recirc capability. automatically initiate . Terminate drill after Cold Leg Operator logs should be accurate, clear and concise. Recirculation is established in ES-1.3. 9
, 2'OMPANY DUQUESNE LI
- Nuclear Power Division Training Administrative Manual
- DRILL 8-98-5 REV 1 - PAGE 19 OBJECTIVE l EXPEC1ED STUDENT RESPONSE- l l INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l r
NOTE: The expected EPP declaration is an ALERT declaration using TAB 1.2.1. A Site Area Emergency would be required if containmen exceeds EAL limits during scenario. e e e S e
- _. ._ . . . - _ . _ _ . _._____ __--_____u-_ _____m_ _ __ .m.__ .m .m _. _ . . - _ . . m. _.___.m.__ _m._.___._. _ m_,_.____
n-l
<s~,
ES-301 Administrative Topics Outline Form ES-301-1 l l Facility: _ Beaver Vallev Power Station Unit 2 Date of Examination: _8/17/98 Examination Level (circle one): RO / SRO Operating Test Number: _2 LOT 2A Administrative Describe method of evaluation:
-Topic / Subject 1. ONE Administrative JPM, OR Description 2. TWO Administrative Questions A.1 Plant Parameter Bank JPM 2CR-017 - Shutdown Margin Verification l
Response & New JPM - 1/20M-48.1.H ' Notification for Potential Tampering A.2 Surveillance Q1 - What are the specific additionaladministrative Testing . requirements for tagging out a D/G in Mode 1 c I (New) ( _ l 02 - Tech Spec 3.06 application (New) b A'3 Approve New JPM - Emergency Exposure Control Emergency Exposure t Protective Action New JPM -PAR A.4 - Recommer'dat,ons i
~() i NUREG-1021 BVPS 2 LOT 2A Revision 1 1 of 1 Interim Rev. 8, January 1997 QD
l-i.i-I/ Q:
' CHANGES TO' ADMINISTRATIVE TOPICS OUTLINE.
; NOTE: All changes to'the original outline are in BOLD /TAL/CS on the revision 1 outline. ;
I-I P
- 1. Question'# 1 of Topic A.2 was changed to an ESF checklist question. The
- PMT question that was originally intended is no longer the responsibility of the NRS, rather this responsibility has been delegated to the new Work
( . Control center, as part of an effort to eliminate the administrative burden on the NSS. O l l l l l I v , I
RTL #A5.640.U ] LEAVER VALLEY JOB PERFORMANCE MEASURE EVALUATOR COVER SHEET JPM Number: 2CR-017 Rev: 1 System #: 001 JPM
Title:
Perform a Shutdown Margin Calculation K/A
Reference:
192002K1.13 3.5/3.7 Task ID #:0010040101 005 AK1.05 3.3/4.1 JPM Application: X Requal X Initial Exam Training Evaluation Method LOCATION TYPE Perform Plant Site O Training O Simulate Simulator O Annual Requal. Exam Classroom O OJT O Initial Operator. Exam Administered By: O Other: BV-T O NRC 0 Other: Evaluation Results Performer: Name: Employee No: Results SAT Time.(minutes) UNSAT* Allotted: 10 $ctual: Time Critical: Yes X No Administrative JPM: X Faulted:
- Comments (Required for UNSAT Evaluation) :
Evaluation Results Check here if same as above Observer 1: Name: Employee No: Observer 2: Name Employee No: Observer 3: Name Employee No: Observer 4: Name Employee No: , Time (minutes) Results Question ID Allotted Actual SAT UNSAT* Question #1 Employee No: Question #2 O Employee No:
- Comments (Required for UNSAT Evaluation) :
Evaluator (Print): Organization: Evaluator Signature Date: After Val
. . - - ~ . . - - , . . . . . . .. --- --. ~ - - - . - - - - - - . - - .-.
l RTL #AS.635.J- BEAVER VALLEY JOB PERFORMANCE MEASURE CANDIDATE DIRECTION S!!EET f
'( ) ,,,/
- THIS SHEET TO BE GIVEN TO CANDIDATE
- Read:
l Task: Perform a Shutdown Margin Calculation i INITIAL CONDITIONS: The plant is at 100% power BOL. One rod is inoperable (immovable and l untrippable). All rods are-fully I' withdrawn. The core is at Beginning-Of-Life with a boron concentration of 1200' ppm. The " Initial Conditions" of the OST are met. INIT. CUE: lYoursupervisordirectsyoutoperformashutdown L g s, margin calculation and determine if the acceptance ( j criteria is met. At this time, ask the evaluator any questions you have on this JPM. When satisfied that you understand the assigne.d task, announce "I am now beginning the JPM". Simulate performance or perform as directed the required task. Point to any indicator or component you verify or check and announce your observations. After determining the Task has been met, announce "I have , completed the JPM". Then hand back this sheet to the evaluator. i hl After Val
. ._ . _ . . - . _ _ - _ _ . . . _- _.m _ _ . . ~ _ __ ._ _ . _ . _ . _ . . _
d i l RIL #AS.635.J BEAVER VALLEY JOL . r'ORMANCE MEASURE [tA EVALUATOR DIRECTION SHEET
\
l V JPM NUMBER: 2CR-017 ! JPM TITLE: -Perform a Shutdown Margin Calculation TASK STAN** The shutdown margin calculation is complete and a correct determination is made when the results are compared to the acceptance criteria. RECOMMENDED i STARTING LOCATION: CONTROL ROOM - DIRECTIONS: You are to simulate (perform) the task Perform Shutdown Margin Chlculation. INIT. CONDITIONS: . - The plant is at 100% power BOL. One rod is l inoperable (immovable and untrippable). All rods are fully withdrawn. The core is at Beginning-of-Life with a boron n concentration of 1200 ppm. The " Initial
' f^
i Conditions" of the OST are met. INIT. CUE: Your supervisor directs you to perform a shutdown margin calculation and determine if the acceptance criteria is met. , REFEkFNCES: Tech Specs 20ST-49.1 Issue 4 Revision 1 TOOLS: Calculator HANDOUT: 20ST-49.1 l l ' rf~%s
'V After Val
, , ... -- . - . . . . - - = . . . .. . - . - _ . . - _ . ~ . - - . .
L- , RTL #A5.635.J. ' i 1 h .' i g'~s. I I ( ) NUMBER TITLE 61 ss l y 2CR-017 Perform a Shut'down Margin Calculation STEP STANDARD (Indicate "S" for' Sat. or "U" ("C" denote's critical' step) for Unsat.). l Start time:
- 1. Obtain shutdown raargin 1. Candidate locates
-form. 20ST-49.1 EXAMINER CUE: The examiner. l
.should give the candidate j the form after he/she has
,_s shown the he/she can find l
-t it. !
- .V)
EXAMINER NOTE: Allow the candidate to calculate the ! shutdown margin and then review the results. A ' reasonable margis of error.
- (math and graph interpretation)-is allowed ;
as long as the method is correct. If the simulator is not being used cue as needed that the plant is at 100% and Rods are at 227 steps on CB "D". The Sample Data Sheet may used to compare results. I-COMMENTS: i ' %E l Page 1 of 4 After Val
RTL #A5.635.J
/ 'T M NUMBER TITLE 2CR-017 Perform a Shutdown Margin Calculation l
l STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step)' for Unsat.) 2'. Datermine Initial Test 2.1 Candidate records.the Prep Data, following data on step A.1 Control Bank D steps (227). Power level (100%) Boron concentration (1200 ppm). Number-of untrippable -l rods a*.(1, O t 5 LJ COMMENTS: i 1
- 3. Calculate the 3. Candidate completes ,
reactivity worth of thr- Step B.1: i
. rods.
-All rods are 227
-Bank Worth is 7.362
-Integral Worth is 0 ,
l
-TBW is 7.362.
-90% Uncertainty is 6.6258.
COMMENTS:
- 4. Determines Power Defect 4. Candidate determines for current boron power defect from concentration and power Figure 1 (between 1.54 level. and 1.58) enters value
-s _ on step B.2. % COMMENTS:
Page 2 of 4 After Val
i l RTL #AS.635.J ? l 1 I
.\ NUMBER TITLE 2CR-017 Perform a Shutdown Margin Calculation l
l STEP: STANDARD l (Indicate "S" for Sat. or "U" ] ("C" _ denotes critical step) for Unsat.)'
- 5. Enter stuck rod worth. 5. Candidate calcula_tes
! the worth of the ; stuck / immovable rods. Adds 1 to A.4-(2) and multiplies by 1.322%. I Enters 2.644 on' Step B.3 l ( (J-1 COMMENTS: . Qwj . I
'6. Calculates'the Shutdown 6. Candidate calculates Margin. . the' Shutdown Margin.
Subtracts Power Defect
. (1.54 to 1.58) and :
Stuck: Rod-Worth (2.644) from 90% Total Bank Worth-(6.6258)
. Enters value on Step B.4 (range 2.4018-1 2.4418) .
. COMMENTS:
l-c-(_/ Page 3 of 4 After Val n y -, - - - , - ~ > -
-. . , . . . _ . . _ . . . . - . . . ~ . . - . - - ~ . ~ . . - . - . . . .
. . - . . ~ . . . ,
l 4 d
- RTL-#AS.635.J O
V NUMBER TITLE l 2CR-017 Perform a Shutdown Margin Calculation i STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.) q l 7.C Determine if SDM is 7.1 Candidate compares adequate. calculated SDM to Acceptance Criteria. 7.2.C Candidate verifies ; that value of the SDM i calculated (2.4**) is 2 to the Acceptance Criteria (1.77):
/ !
-} 7.3 Informs supervisor of ;
's SAT test completion.
7.4 Completes ti:e OST Cover. COMMENTS: . I i EXAMINER NOTE: The last two 1 substeps may be omitted. i I
- Stop Time
' ' p. G Page 4 ot 4 After Val l I l' .- . - , -, , . , , - _
i , l- ' l I i Record Type #A9.330B
- 4 DUQUESNE LIGHT COMPANY i Beaver Valley Power Station Unit 2 i FORTRAIN NG USE ONil , .
2OST-49.1 l Shutdown Margin Calculation (Plant Critical) (Updated For Cycle 7) O lasue 4 Revision 1 Prepared by Date Pagesissued Effective Date G. T. Wiggins 10/01/96 1 through 12 ) O - 5 Cl le Reviewed by. Date Validated by Date - C. R.- Kuhn 10/01/96 R. W. Huston 10/01/96 OSC Meeting No. Date Approved by Date BV-OSC-40-96 10/02/96 gg g gg L I Lo masm
!W2NN2
- . ~. - . . . . . - - . _ . - . _ _ . - - . . ~ . . .
L . 1 .' Bsaver Valley Power Station Unit 2 2OST-49.1 ' Issue 4 Revision 1 Operating Surveillance Test Page il
} Shutdown Margin Calculation (Plant Critical) v- (Updated For Cycle 7)
Table of Contents
- 1. PURPOSE ... .... .... . .. .... . ... .... ... . 3
- 11. DISCUSSION . ... .............. . . ... .... ..... ... . 3 l Ill. ACCEPTANCE CRITERIA ... .. . ...... . ..... .. . . ... . 3 IV. EQUIPMENT AND MATERIAL ... ....... .. ... .. ......... 3 V. PRECAUTIONS AND LIMITATIONS .. ... . ...... .. .......... 3 VI. INITIAL CONDITIONS ..... . ...... . .. . . ..... ..... 4 Vll. INSTRUCTIONS . ..... . .. . ... . . .... . . ... . 5 Vill. DATA SHEETS, TABLES, FIGURES, AND ATTACHMENTS .. . .. ...... 6 DATA SHEET 1 . ......... ........... . ... . . .. ........ 7 FIGURE 1 .
... .............. .... ... . ..... . ..... ... 8
. FIGURE 2A . . ..................... .... .... ....... ........ 9 FIG U R E 2 B . . . . . . . . . . . . . . . . . . . . . ... . . .. ..... ........ . 10
- . FIGURE 2C . . . . ..................... .... ......... . .. . 11
.IX. REFERENCES . . ............... .. ....... .... .. ..... 12 I
i l I I' 2 L @@NB@l2 l l NF2 BEN @ v Table of Contents
fdL# A9.330C OPERATING MANUAL CHANGE NOTICE 1/20M.48.2.B-2 / Check Applicable Unit O Unit 1 (White) O
, W Unit 2 (Blue) j O Unit 1/2 (Pink)
Chapter, Section & Procedure 6 fA , h ~2. o 5 7 // 9 / ) Issue 4/- Rev. / Annunciator Window No. p/jf . I intent Change? O YES M NO. '
-(if NO., Perform and attach a Non-intent Veri 5 cation fonn)
Does this change conflict with the UFSAR (Elther Agures OR Text)?" , O YES M NO (If YEs. perform a Safety Evaluation (10CFR50.59) screening in so ordance with NPDAP 8.18) Does this change affect a VOND?" O YES SK NO (if YES. Inidate a VCN) Does this OMCN change an NSA?" O YES T NO (if yE._s_, perform a Safety Evaluation (10CFR50.59) screening in accon%nce with NPDAP 8.18) is this change in respor.se to, OR changes a Regulatory or DLC Commitment? ji[ YES .O NO
- (if YEs. Identify the Commitment document and basis) 8/f 9~//S O2 . #' E / - 7"' ^ / "' ~~ ^ ' MJIcE 7 l
This is Page 1'of .3 Pages RECORD ALL OF THE ATTACHED PAGES: Q '4 ~ I REASON FOR CHANGE-Anns Vo7c- n A-a;r77xJer c;er,,.,z,A ry su wi,es, rs 4 /, /, / /.a fewMona , codr/hewwr** Wenv z o s 7 - W9. 2 A uAt/ 7~ / rnm2:2 ORIGINATOR _ G . [ 2/2,-6 / Employee No. 4 /7/fB
- SPED ENGINEER E REQUIRED FOR ALLINTENT i
I PLANT STAFF
- h1 (P 8 $ CHANGES TO OST's OR l
MEMBER Employee No. DATE OTHER PROCEDURE THAT
- S{GNATURE
] 4 M IMPLEMENTS ATECH SPEC SURVEILLANCE.
VUNIT 1 SRO** /t// SIGNATURE Employee No. DATE "SHOULD BE SYSTEM SR'O UNIT 2 SRO** b,[ y ;o r s/g/fg IF AVAILABLE PRIOR TO SIGNATURE Employee No. ' DATE NEED. OSC REVIEW BV-OSC- % 5t'11 COMMENTS men Ld. m.1 m 4. G-iz-f8 MEETING No. DATE Unreviewed Safety Question O YES E NO OSC Approval Recommended El YES O NO
$ Ap ro d /~ / 3-.8 f a Disapproved l j , Lg ~} ?
_ General M3trafer Nuclear Ops Employee No. General Manager Nuclear Ops Employee No.
~
NOTE: INTENT changes REQUIRE GMNO approval PRIOR to implementation. ~ NON-INTENT changes REQUIRE GMNO apprgvalwithin 14 days of Effective Date. s this OMCN Change an Operator Ald? O YES ho The revision used for this OMCN is current. IYES Does this OMCN Change a Ctation Log? O YES GTNO . Prior to assignment of the OMCN number, this form has been administratively reviewed for applicable form leteness in accordance with the instructions on the back. com[UN 8 1998 fgdo Number OMCN- 8 - 98 -
/ff Effective Date Time This Section completed by: [/MA44- M /tEMmb _
Print Name Signature - Aff7 Employee No. _ SYSTEM SRO REVIEW: O Approved COMMENTS: (Required for OMCRs Rejected) O Rejected (Provide Reason in Comments Area) a Approvedwith Attached Comments
.. .rm 1 rarn Q)Wlil ~ W.blj.$W SYSTEbl SRO Date 1/2OM-48.2.B-2, Revision 14 48_2_B2
- l. ,
j 8::,v:r Valley Powar Station Unit 2 2OST-49.1 i issue 4 Revision 1 l Operating Surveillance Test Page 1 of 12 I (T ' Shutdown Margin Calculation (Plant Critical) i' (Updated For Cycle 7) l t-l Frequency: SPO Surveillance Requirements: 4.1.1.1.1.a Required for Mode (s): 1,2# Date / Time Completed: / Performed in Mode (s): 1,2# Total Manhours: TEST RESULTS: (Completed by Performer) PERFORMED BY: Name (Print) Initia_I or N/A) O Test Completed SATISFACTORY O
~
Problems Encountered (See Problem Sheet) O Unscheduled / partial OST (explain)
/"%,
Reviewer Signature /Date ,[W] STA Review / NSS Approval / CCMMENTS- (Incluoe Date and initials) i a O Comments cor.tinued on Problem Sheet
- O See T.S. 4.1.1.1.1.a - Within one hour after detection of an inoperable control rod (s) and at t
least once per 12 hours thereafter while the rod (s) is inoperable.
#- With Keff 2: 1.0.
P
@@ERMB BW2@SV2
.._... - f .--
v s+. o Bezver Vallay Powgr Statisn -
~ Unit 2 I 20ST-49.1 Operating ~ Surveillance Test Issue 4 Revision 1 O.' ~
" Shutdown Margin Calculation (Plarit Critical) ~
~
~ ~ ~ ~' ~ ~
"~ Pa
~ ~ ~ge 3 of 12 V (Updated For Cycle 7) i l
- 1. PURPOSE To determine the shutdown margin when the reactor.is critical within one hour after' ..
l detection of an inoperable rod (s) and at least once per 12 hours thereafter.while the rod (s) is inoperable. To determine the shutdown margin when the reactor is shutdown, use
. 20ST-49.2, " Shutdown Margin Calculation (Plant Shutdown) (Updated for Cycle 7)". .
.. l lI. DISCUSSION This shutdown margin calculation does not include the reactivity effects of Xenon, .
Samarium or Boron, therefore, it is only accurate to determine the shutdown margin due to , the insertion of control rods only. The reference condition for the shutdown .rn'arginf l calculation is the just critical condition at zero power, Tavg at 547'F and 2235 psig RCS
. pressure.
Ill. ACCEPTANCE CRITERIA - Note: If any control rods are declared inoperable due to being immovable or untrippable, the required shutdown boron concentration shall be increased by an amount at least equal to the withdrawn worth of the immovable or untrippable control rods. This will be accomplished by adding (p x n) %Ak/k to the required shutdown boron concentration where p is the reactivity worth of the most reactive )g l rod and n is the number of immovable or pntrippable rods. The shutdown margin shall be determined to be greater than this required margin within 1* hour after y g detection of the inoperable control rods and at least once per 12 hours thereafter while the :ods are inoperable.(c.4 4 A. The shutdown margin shall be 21.77% Ak/k. (Step B.4) (T.S. 4.1.1.1.1.a)
, IV.. EQUIPMENT AND MATERIAL NONE ,
l V. PRECAUTIONS AND LIMITATIONS A. . If the shutdov,n margin < 1.77% Ak/k, immediately initiate and continue boration at 2 30 gpm of 7000 ppm boric acid solution or equivalent until the required shutdown margin is restored. ' 1. Reference 20M-7.4.Q, " Emergency Boration" or 20M-7.4.K, " Blender Boration Operation".
' B. To determine the shutdown margin when the reactor is shutdown, Perform 20ST-49.2,
" Shutdown Margin Calculation (Plant Shutdown) (Updated for Cycle 7)".
iO OMCN 2-93
- PAGE A OF A
~ =,' '.- l
- \
Be:v:r Vcil:y Pow:r Station Unit 2 i 2OST-49.1 Operating Surveillance Test Issue 4 Revision 1 A Page 4 of 12 l Shutdown Margin Calculation (Plant Critical)
- (Updated For Cycle 7)
) VI. INITIAL Coi4DITIONS A. Plant Status Chanaes This procedure does not affect plant status. . B. NSSIANSS Slan-on
- 1. The reactor is critical.
- 2. NSS/ANSS verifies the following: -
l
= Requirements of Section VI.B, NSS/ANSS Sign-on have been verified. l
- Performance of this proce' dure is authorized.
i DATE: ilME: CURRENT PLANT MODE: NSS/ANGS COMMENTS:
. l 1
{( NSS I ANSS Signature C. Reactor Operator Slan-oD o
- 1. Reactor Operator perform the following:
- Acknowledge procedure performance.
Retetor Operator Signature D. Procedure Performer initial Conditions
- 1. The operator (s) performing this test have reviewed this procedure.
/
Initial / Date
~
I InitialI Date l CM0bl PAGF 10F 2-]9F- /19 , 1
Buver Valley Power St: tion Unit 2 20ST-49.1 issue 4 Revision 1 Operating Surveillance Test Page 5 of 12 Shutdown Margin Calculation (Plant Critical) ? *
/^)\
's (Updated For Cycle 7)
[ Vll. INSTRUCTIONS A. Test Preparation
- 1. Record the number of steps withdrawn for Control Bank D (OR Control Bank C IF CBD is at 0 steps) from the group demand counters, (BB-B) on Data Sheet 1.
I initial / Date
- 2. Record the current reactor power level in percent of full power from -
. [2NME-NR45], Reactor Excore Recorder, (VB-B) OR PCS computer point U1150, PWR RNG NUCLEAR FLUX 1M AVG, on Data Sheet 1. -
I initial / Date
- 3. Record the current RCS Boron concentration in ppm on Data Sheet 1.
I initial / Date
- 4. Record the number of immovable OR untrippable control rods on Data Sheet 1.
Initial / Date B. Shutdown Marain Calculation
- 1. Determine control bank reactivity worth per the following:
Note: Current core burnup may be obtained from the Reactor Engineering Data Book
, located in the NSS's office.
- a. Using the Total Bank Worth table on Data Sheet 1, Enter the total bank worth for the current core burnup range, (BOL, MOL, or ECL) in the space provided on Data Sheet 1.
Note: If control rods have been inserted in Individual Bank Select instead of normal overlap, obtain integral rod worth for the inserted bank from Curve Book figures CB-11D,11E, or 11F, " Integral Rod Worth vs. Steps Withdrawn BOL (MOL) (EOL), HZP, Control Banks A, B, C, & D" instead of Figure 2.
- b. Using Figure 2A,28 OR 2C, Determine integral rod worth for the current bank position AND Enter this value on Data Sheet 1.
- c. Subtract the integral rod worth from the Total Bank Worth AND Enter the
! V
'O result on Data Sheet 1.
- d. Multiply this result by 0.9 to apply a 10% uncertainty AND Enter the result on Data Sheet 1.
- 2. Using Figure 1, Determine the Power Defect for the current power level and Boron concentration AND Enter this value on Data Sheet 1.
l .- '. Bsivar Vallsy Power Station Unit 2 20ST-49.1 I? Issue 4 Revision 1 !' Operating Surveillance Test Page 1 of 12 l /7- . Shutdown Margin Calculation (Plant Critical) l - (g) ~ (Updated For Cycle 7) Frequency: SPD Surveillance Requirements: 4.1.1.1.1.a Required for Mode (s): 1,2# Date / Time Completed: / Performed in Mode (s): 1,2# Total Manhours: TEST RESULTS: (Completed by Perlormer) PERFORMED BY: Name (Print) Initial o' N/N 0 l Test Completed S ATISFACTORY l
~
0 Problems Ercountered (See Problem Sheet) O Unscheduled / partial OST (explain) 'b Reviewer Signature /Date b:N STA Review / NSS Approval _. / COMMENTS: (Include Date and initials) l I O Comments continued on Problem Sheet O See T.S. 4.1.1.1.1.a - Within one hour after detection of an inoperable control rod (s) and at
-least once per 12 hours thereafter while the rod (s) is inoperable.
# With Keff 2: 1.0.
O oV
@@Em@[A[B WW@ @EN 2
Braver Vallsy Power Stttion Unit 2 2OST-49.1 k issue 4 Revision 1 > Operating Surveillance Test Page 2 of 12 Shutdown Margin Calculation (Plant Critical) (Updated For Cycle 7) (- OST PROBLEM GHEET See Page and Step No. for problem description. See below for corrective action, e.g: MWR No., OMCN No., OMCR or Database change written or other. PAGE NO. STEP NO. DESCRIBE CORRECTIVE ACTION INITIALS DATE 9 e O 1
y - - - - . ...
-..._.__w 1
D:cvar Vall y Pow:r Stitinn - Unit 2 2OST-49.1 I Operating Surveillance Test issue 4 Revision 1
~~Page~~~"3 of 12
" Shutdown Margin Calculat!on (Plarit'CritiEal) ~
~
~ ~ ~^ ~^ ,
-~
\ (Updated For Cycle 7) )
i
- 1. PURPOSE To determine the shutdown margin when the reactor.is critical within one hour after' .
detection of an inoperable rod (s) and at least once per 12 hours thereafter while the rod (s) is inoperable. To determine the shutdown margin when the reactor is shutdown, use 20ST-49.2, " Shutdown Margin Calculation (Plant Shutdown) (Updated for Cycle 7)". -
.. l
- 11. DISCUSSloN This shutdown margin calculation does not include the reactivity effects of Xenon, . l Samarium or Boron, therefore, it is only accurate to determine the shutdown margin due to l the insertion of control rods only. The reference condition for.the shutdown niargin.
~
j calculation is the just critical condition at zero power, Tavg at 547'F and 2235 psig RCS pressure. 111. ACCEPTANCE CRITERIA - Note: If any control rods are dec!ared inoperable due to being immovable or I untrippable, the required shutdown boron concentration shall be increased by an amount at least equal to the withdrawn worth of the immovable or untrippable f-control rods. This will be accomplished by adding (p x rf) %Ak/k to the required shutdown boron concentration where p is the reactivity worth of the most reactive hg rod and r; is the number of immovable or pntrippable rods. The shutdown margin shall be determined to be greater than this required margin within 1' hour efter y g detection of the inoperable control rods and at least once per 12 hours thereafter while the rods are inoperable.<c.i) + A. The shutdown margin shall be 21.77% Ak/k. (Step B.4) (T.S. 4.1.1.1.1.a)
, IV. EQUIPMENT AND MATERIAL NONE ,
V. PRECAUTIONS AND LIMITATIONS A. . If the shutdown margin < 1.77% Ak/k, immediately initiate and continue boration at & 30 gpm ci 7000 ppm boric acid solution or equivalent until the required shutdown margin is restored. 1. Reference 2OM-7.4.Q, " Emergency Boration" or 20M-7.4.K, " Blender Boration Operation". B. To determine the shutdown margin when the reactor is shutdown, Perform 20ST-49.2,
" Shutdown Margin Calculation (Plant Shutdown) (Updated for Cycle 7)".
O OMCN 2-98 M PAGE A OF 3
- ~
Benvar Villsy Pow:r Station Unit 2 1 i 20ST-49.1 Operating Surveillance Test Issue 4 Revision 1 Page 4 of 12 Shutdown Margin Calculation (Plant Critical) s .,j s (Updated For Cycle 7) i VI. INITIAL CONDITIONS A. Plant Status Chanaes This procedure does not affect plant status. . B. NSS/ANSS Slan-on
- 1. The reactor is critical.
- 2. NSS/ANSS verifies the following: -
- Requirements of Section VI.8, NSS/ANSS Sign-on have been verified.
- Performance of this proce' dure is authorized.
DATE: TIME: CURRENT PLANT MODE: NSS/ANSS COMMENTS: t (V Reactor Operator Slan-on NSS / ANSS Signature C.
- 1. Reactor Operator perform the following:
- Acknowledge procedure performance.
Reactor Operator Signature D. -Procedure Performer Initial Conditions '
- 1. The operator (s) performing this test have reviewed this procedure.
I initial / Date I initial / Date OWN 2 /19 PAGE A_OF A
l w _ . - - .l l Bs:vsr Valley Powar St: tion Unit 2 20ST-49.1 l Issue 4 Revision 1 Operating Surveillance Test Page 5 of 12 O V Shutdown Margin Calculation (Plant Critical) (Updated For Cycle 7) I* l Vll. INSTRUCTIONS A. Test Preparation
- 1. Record the number of steps withdrawn for Control Bank D (OR Control Bank C IF CBD is at 0 steps) from the group demand counters, (BB-B) on Data Sheet 1. i
/
Initial / Date
- 2. Record the current reactor power level in percent of full power from -
[2NME-NR45], Reactor Excore Recorder, (VB-B) OR PCS computer point U1150, l PWR RNG NUCLEAR FLUX 1M AVG, on Data Sheet 1. -
/
Initial / Date , i
- 3. Record the current RCS Boron concentration in ppm on Data Sheet 1. i i
Initial / Date !
- 4. Record the number of immovable OR untrippable control rods on Data Sheet 1.
Initial / Date B. Shutdown Marain Calculation
- 1. Determine control bank reactivity worth per the following:
Note: Current core burnup may be obtained from the Reactor Engineering Data Book
. located in the NSS's office.
- a. Using the Total Bank Worth table on Data Sheet 1, Enter the total bank worth for the current core burnup range, (BOL, MOL, or EOL) in the space provided on Data Sheet 1.
F. i4ote: If control rods have been inserted in Individual Bank Select instead of normal overlap, obtain integral rod worth for the inserted bank from Curve Book figures CB-11D,11E, or 11F, " Integral Rod Worth vs. Steps Withdrawn BOL (MOL) (EOL), HZP, Control Banks A, B, C, & D" instead of Figure 2.
- b. Using Figure 2A,28 OR 2C, Determine integral rod worth for the current bank position AND Enter this value on Data Sheet 1.
- c. Subtract the integral rod worth from the Total Bank Worth AND Enter the l [3 result on Data Sheet 1.
IV d. Multiply this result by 0.9 to apply a 10% uncertainty AND Enter the result on Data Sheet 1.
- 2. Using Figure 1, Determine the Power Defect for the current power level and Boron concentration AND Enter this value on Data Sheet 1.
4 B::v r Vsliny Powcr St:tirn Unit 2 20ST-49.1 issue 4 Revision 1 Operating Surveillance Test Page 6 of 12 Shutdown Margin Calculation (Plant Critical) (\ (Updated For Cycle 7)
- 3. Add one to the number of immovable or untrippable control rods AND Multiply the result by the worth of the most reactive control rod (givan on Data Sheet 1)
AND Enter the result on Data Sheet 1.
- 4. Subtract power defect and stuck rod (plus immovable or untrippable rod) worth from the current total bank worth AND Enter the result on Data Sheet 1.
C. Test Completion
- 1. Consult the Acceptance Criteria for acceptable performance. _.
/
Initial / Date
- 2. If the shutdown margin < 1.77% Ak/k, immediately initiate and continue boration at 2: 30 gpm of 7000 ppm boric acid solution or equivalent until the required shutdown margin is restored. Reference 20M-7.4.Q, " Emergency Boration" or 20M-7.4.K," Blender Boration Operation", (otherwise, N/A this step).
/
Initial / Date
- 3. Inform the NSS/ANSS of the completion of this test.
/
initial / Date (G
- 4. Complete the front cover sheet.
/
Initial / Date Vill. DATA SHEETS, TABLES, FIGURES, AND ATTACHMENTS A. Data Sheets
- 1. Shutdown Margin Calculation B. Tables NONE C. Flaures
- 1. Figure 1 - Power Defect vs. Percent Power at BOL, MOL, and EOL
- 2. Figure 2A-Integral Rod Worth vs. Steps Withdrawn Banks D and C Moving with !
Overlap No Xenon, BOL, HZP
- 3. Figure 28 -lategral Rod Worth vs. Steps Withdrawn Banks D and C Moving with l Overlap No Xenon, MOL, HZP
- 4. Figure 2C - Integral Rod Worth vs. Steps Withdrawn Banks D and C Moving with Overlap No Xenon, EOL, HZP D. Attachments NONE
Beavor Valley Power Station Unit 2 20ST-49.1
~
Operating Surveillance Test issue 4 Revision 1 Page 7 of 12 Shutdown Margin Calculation (Plant Critical) (Updated For Cycle 7) DATA SHEET 1 SHUTDOWN MARGIN CALCULATION A.1. C,3D Steps Withdrawn (OR CBC if CBD @ 9 steps) = STEPS
- 2. Reactor Power = %
- 3. RCS Boron Concentration = __ ppm
- 4. Number ofImmovable or Untrippable Rods =
ROD (s) .. ARO TOTAL BANK WORTH (% Ak/k) BOL,HZP MOL, HZP EOL,HZP 0 to 4000 MWD /MTU 4001 to 12000 MWD /MTU 12001 MWD /MTU to EOL 7.362 7.565 8.177 B.1. a. ARO Total Bank Worth (See Table above) (TBW) = % Ak/k
- b. Integral Rod Worth (Figure 2A,28, OR 2C) (IRW) = % Ak/k gg c. TBW (1.a) - IRW (1.b) = % Ak/k
- d. 90% Current Total Bank Worth 0.9 x (1.c) = % Ak/k
- 2. Po ver Defect (from Figure 1) = % Ak/k
- 3. { Worst-Case Stuck Rod + (Immovable or Untrippable Redc)) x Most Reactive Rod Worth
{1 + (A.4)} x 1.322% Ak/k = % Ak/k
- 4. SHUTDOWN MARGIN (Acceptance Criteria 2: 1.77% Ak/k)
(90% Total Bank Worth)-(Power Defect)-(Stuck Rod (s) Worth) (B.1.d) (B.2) (8.3) ( 1-( 1-( )
= % Ak/k (1) I initial I Date (2) I initialI Date O
LJ t DATA SHEET 1
Unit 2 20ST-49.1 Bn:ver Vallsy Power Station issua 4 Rsvision 1 Page 8 of 12 Operating Surveillance Test Shutdown Margin Calculation (Plant Critical) (Updated For Cycle 7) ( FIGURE 1 POWER DEFECT vs PERCENT POWER at BOL,'MOL, and EOL . Unit 2, Cycle 7 - 2.8 _ _
+- - - - . ----- -
- - :r*+ U ,
0 ppm
- .-.-.H. ,
g_ - r
----4 p.--
44 _- . , . . 2'6 - / -- -
? 4 a _.g: 200 ppm w
+s+ /g .
.p..L-24'
! >' e 400 ppm
_ a- / -2 4 ,, 1 -
'7)--{4 2.2
.g.___ _____ __ 4 g ,' ;; ' -y:l 600 ppm
+. -
.+ , p;,g_ g- 9
+-... -+ + , -- ety ...,,
2.0 jg.
- ~
7 , o< i -/ -
; 800 ppm x[1.8 x
f:$i-4 _- _ 4__. ; +[-i
=4 554*
p 1000 ppm r - - r.. fg-y , . c e,a,o -
-f+' :,. _q-3 ..
p' .,,-' +
-a.7-9 ,
g -~t-M' ~+---+ A ' -
,A++-
, , ,' .j_-
y 1.6 _7:: M,_ .9 _ _g.- g 1200 ppm _- :p. - m . m - - No,,o
~~
- vm. .
r ,, -+m- -- -- a..+_- e: y-a w-o I'4 y'. 9 i~y&- gyp 5,- Mix yty-d' y.g- --
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- 1600 ppm
= ~~
c _3.
.,a,-1 my n y 9.
c- - Q 1.2 .-= -;e l}#f
-1 n
, , 3 , : j_.
p + .~ u, st%@dg h; y.: __g o i wt :' v 3: 7p- +- - n ! _
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-+vr- <
' ." -+- : :
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-y+- g4:aA[; -
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- 9
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- - - -- ;. . - 2
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""" ~ *~ ~" '" ~~ ~
# ~ ~
0 10 20 30 40 50 60 70 80 -{ } 90 100 Power Level (percent of full power) ( FIGURE 1
8:rver Valley Pow:r Station Unit 2 20ST-49.1 issue 4 Revision 1
. Operating Surveillance Test Page 9 of 12
~
Shutdown Margin Calculation (Plant Critical) fw (Updated For Cycle 7) FIGURE 2A Integral Rod Worth vs Steps Withdrawn Banks D and C Moving with Overlap
~
No Xenon, BOL, HZP .. 1.75 , . . I V 1.50 3s , ,
.. . _..t y -h -- ... __.
M 1
' I ' '
$ '25
\ .L d,l. 3. .._.L N --
i
~~~1 g] $ __. \- ___ ..._._._ f l
_f.22$ () g ..- . v 1.00 g . .- h _-- __ u ._. . ._.- _ _j.. _ _ . ._._ _. t 0.75 ' 3
._N._._._ _ __ .
_.{__
~~
a N 8 \
~
[ 0.50
- \ N f
.5 \
\
\ _
0.25
\
Al
\
\
0.00 I cac 0 25 50 75 100 125 150 175 200 225 Bank D Rod Position Steps Withdrawn rm ,y BOL = (0 - 4000 MWD /MTU) FIGURE 2A
Unit 2 20ST-49.1 Bravor Vallny Powar Station issue 4 Revision 1 Page 10 of 12 Operating Surveillance Test Shutdown Margin Calculation (Plant Critical) (Upda'.ed For Cycle 7) ( FIGURE 2B Integral Rod Worth vs Steps Withdrawn Banks D and C Moving with Overlap No Xenon, MOL, HZP - 2.* ,, _q. 1.75 N i
._-g .__.
._(-
_y - 2' \L ! __. l_t I l g ...
\<__.. l l -
T3 _ ... _ ._.
} .g _ . . ... __.__.. _ ._ __._._.--.
o _._. O 1.00 ,
\i , ,
._qg _._. ._
o __.. . _. __s q.____ _ _ _. __ O - --. .- T 0.75 Em b ,M g N__s\ g _ N c 0.50 .l. N 1 . N
~[_.
I ( ~~ K(, ; I 0.25 i l _ l ~
\
l l_ . 0.00 csc 0 25 50 75 100 125 150 175 200 225 8'" Bank D Rod Position Steps Withdrawn ( i MOL = (4001 - 12000 MWD /MTU) FIGURE 28
l . 1
- Beaver Valley Power Station Unit 2
' 20ST-49.1
. Operating Surveillance Test Issue 4 Revision 1 Page 11 of 12 Shutdown Margin Calculation (Plant Critical) l [,,h (Updated For Cycle 7) 1 Q'
FIGURE 2C Integral Rod Worth vs Steps Withdrawn Banks D and C Moving with Overlap No Xenon, EOL, HZP 2*50
,' _L- '
_-.{ , yl-F...._ _{... _ . l _.
'J._ _
i - - 2.2s _A; , x,; , p g_, . _+ . ._
.y E,m 2 00 '
~
t i i \1 i ',' 2 -
~'
' T' i
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~
__.7 _ __ _p l y-}- ' g 1.75
,k,,
\\ , __
p _{ f- ..-_. .
-::11:.. TU
[V 4\. __ ..p . p. _h .___.
;.1_h.Q:.f.[ 7.. .. p p..
6 150 q 4_-- _ . . __.__ _4 . _g. . .. _4.g.-
- --H H- -;-riF
.c Tr --
g: 1 _c
- Tcr
!l -- -}\- i+p::l t r-i -
-H-ht -h--
j ** 4'p__ _J -N;- .._ fp. i _'t j , l l p g l j. ~. ~.[ x- ;; - N l H- _g gS-l g . . .-_. _L __ _ . i - CD 0.75 , A ii j -d-O i
, g, ,
w g si h K ____.___ l' 0.50
' ~
i i b I i i l' I i 0.25 ll
.i i
i i-
~~
0.00 i
. i
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cBC 0 25 50 /5 100 125 150 175 200 225 8'" Bank D Rod Position Steps Withdrawn R) t EOL = (12001 - 17000 MWD /MTU) FIGURE 2C
Unit 2 2OST-49.1 Beav:r Vcil y Power Station issue 4 Revision 1 Page 12 of 12 ' Operating Surveillance Test f Shutdown Margin Calculation (Plant Critical) ( (Updated For Cycle 7) IX. REFERENCES A. TECHNICAL SPECIFICATIONS
- 1. BVPS-2 T.S. 4.1.1.1.1.a B. UPDATED FINAL SAFETY ANALYSIS REPORT .
- 1. 4.3.1.5 C. COMMITMENTS NONE D. ADMINISTRATIVE
- 1. QA Audit No. BV-1-87-06, Observation No. 3 E. VEN00R INFORMATION
- 1. WOAP 14714,"The Nuclear Design and Core Management of the Beaver Valley Unit 2 Power Plant - Cycic 7" F. DRAWINGS NONE G. OPERATING MANUAL
- 1. 20M-7.4.K, Blender Boration Operation
- 2. 20M-7.4.Q, Emergency Boration
'3. 20ST-49.2, Shutdown Margin Calculation (Plant Shutdown) (Updated For Cycle 7)
- 4. 10ST-49.1, Shutdown Margin Calculation (Plant Critical) (Updated For Cycle 12) l H. PLANT MODIFICATION NONE .
I. OTHER
- 1. OMCR 2-96-1089, (Issue 4/Rev.1) e t
1 l l RTL #AS.640.U BEAVER VALLEY JOB PERFORMANCE MEASURE EVALUATOR COVER SHEET l JPM Number: Adm-Tamper Rev: 0 System #: 2.4 JPM
Title:
Response & Notification to Potential Tampering or j Mispositioning Event K/A
Reference:
2.4.28 2.3/3.3 Task ID #:344JJJ0302 JPM Application: X Requal X Initial Exam Training l l Evaluation Method LOCATION TYPE Perform O Plant Site Training l j O Simulate Simulator Annual Requal. Exam j O Classroom OJT l l Initial Operator Exam
'dministered By:
A Other: ! BV-T 2 NRC i Other: l Evaluation Results i t j Performer: Name: Employee No: j Results SAT Time (minutes) i l UNSAT* Allotted: 10 Actual: ! Time Critical: Oves x No f Administrative JPM: S Faulted: !
- Comments (Required for UNSAT Evaluation):
- l. .. .
l Evaluation Results Check here if same as above
- Observer 1
- Name: Employee'No:
j Observer 2: Name Employee No: 4 Observer 3: Name Employee No: , Observer 4: Name Employee No: Time (minutes) Results Question ID Allotted Actual SAT UNSAT* Question #1 Employee No: Question #2 O Employee No:
- Comments (Required for UNSAT Evaluation):
Evaluator (Print): Organization: Evaluator Signature Date: After Val
l L RTL #AS,635.J- BEAVER VALLEY JOD PERFORMANCE MEASURE f l lp CANu.DATE DIRECTION SHEET
- THIS SHEET TO BE GIVEN TO CANDIDATE
- i Read:
l -. I Task: l Response & Notification-toPotentialTamperingor ! Mispositioning Event INITIAL CONDITIONS: lTheplantisat.100% power, all systems in NSA. "A" HHSI pump is running with "B" HHSI. pump in Standby. "C" HHSI pump is unavailable. The PAB operator has called to report that the service water supply valve.to the "B" HHSI pump' lube oil cooler (2SWS*164] is locked SHUT. He ' thinks it should be locked OPEN. There have been No maintenance activ.ities, or OST's run on either service water or the HHSI pumps in the last 30 days. 7 _ L/ I IT. CUE: lAstheNSSyouaretorespondtothisreportby implementing the appropriate administrative procedure. 1
~"
At this time,.ask the evaluator any questions you have on this F --- JPM. )
~~
When satisfied that you understand the assigned task, announce "I am now beginning the JPM". Simulate performance or perform as directed the required task. - Point to any_ indicator or component you verify or check and announce your observations. After determining the Task has been met, announce "I have
. completed the JPM". Then hand back this sheet to the evaluator.
l. x_ J . l-After Val
RlL #AS.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE ('3 EVALUATOR DIRECTION SHEET \- 4
.JPM' NUMBER: Adm-Tamper i
JPM TITLE: Response & Notification to Potential j Tampering or Mispositioning Event l A STAN.: Implement 1/20M-48.1.H, and Notify Security, Plant Management, and' initiate a CR
. RECOMMENDED.
STARTING LOCATION: CONTROL ROOM , j DIRECTIONS: You are to simulate (perform) the task Response & Notification to Potential l Tampering Event j INIT. CONDITIONS: The plant is at 100% power, all systems in NSA. ."A" HHSI pump is running with "B" HHSI pump in Standby. "C" HHSI pump is unavailable. The PAB operator has called to report that the service water supply valve 7-s . t to the "B" HHSI' pump lube oil cooler
\. / (2SWS*164) is locked SHUT. He thinks it should be locked OPEN. There have been NO-maintenance activities, or OST's run on either- service water or the HHSI pumps in ;
the last 30 days, j INIT. CUE: As the NSS you are to respond to this l report by implementing the appropriate i administrative procedure. I
REFERENCES:
1/20M-48.1.H issue 4 rev. O TOOLS: , l HANDOUT: 1/20M-48.1.H issue 4 rev. 0 l r~s - After Val
L ! RTL #A5.635.J
,rh \~- NUMBER TITLE ADM-Tamper Response & Notification to Potential Tampering or Mispositioning Event L STEP STANDARD (Indicate "S" for Sat. or "U"
("C" denotes critical step) for Unsat.)
, Start time:
EXAMINER NOTE: Candidate may reference NPDAP 5.9
" Reporting & Notification of Potential Tampering or.
Mispositioning Event" before locating procedure. NPDAP 5.9 will instruct the candidate to reference to
.(' implement Procedure 1/20M-48.1.H.
- 1. Obtain Procedure 1. Candidate locates Procedure 1/20M-48.1.H ,
1
- 2. Dispatch an operator 2. Contact PAB operator, l
.to limit access and instruct to limit l leave valve as found. access-and leave valve I as found.
l l EXAMINER CUE: Role play PAB - operator. You will limit access and leave valve as found. COMMENTS: l(NV. Page 1 of 4 After Val
.. .. . . _ . . . . . . - . . . .--- ~. . - .- .. _ .
RTL #AS.635.J'
. C\ '
N- NUMBER TITLE ADM-Tamper Response & Notification to Potential Tampering or Mispositioning Event STEP ~ STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical sten) for Unsat.) . 3.C Utilize figure 48.1.H-1 3.1 Candidate should use to determine figure 4'8.'1.H-1 to appropriate level of answer-the following required actions and questions: notifications. 3.2 Does this involve a locked component? i,O) EXAMINER NOTE: Answer should be YES 3.3 Is there evidence of recent work history? EXAMINER NOTEi Answer should be NO (from initial conditions). 3.4 Is there evider.ce of recent operations history? i l-EXAMINER NOTE: Answer i s. f'T
\_s/
should be NO (from initial conditions). I Page 2 of 4 After Val
.RTL #AS.635.J \s- NUMBER TITLE ,
ADM-Tamper Response & Notification to Potential Tampering or Mispositioning Event O. STEP STANDARD (Indicate "S" for Sat, or "U" ("C" denotes critical step) for Unsat.) 3.5 Is the event- . explainable? EXbMINER NOTE: Answer should be NO (from initial conditions there is no evidence to supp' ort a yes
~%
answer).
'~
3.6.C NSS determines that Security supervisor must be notified, and contacts security supervisor. EXAMINER CUE: Role' play Security supervisor and accept notifiuotion.
.3.7.C NSS determines that .
~ Plant Management must be notified, and contacts Plant Manage, ment f
l EXAMINER CUE: Role play 1 Plant Management and accept I s notification. ,h ,/' -- Page 3 of 4 After Val l L i L- t
RTL #A5.635.J N Y'j i NUMBER TITLE ADM-Tamper Response & Notification to' Potential
- Tampering or Mispositioning Event STEP STANDARD (Indicate "S" for Sat. or "U"
("C" denotes critical step) for Unsat.)
~
3.8.C NSS determines that a , Condition Report must be initiated, and initiates a Condition Report. J
~l l
EXAMINER CUE: Inform i candidate that it is not necessary to fill out the
,r s condition report at this ,
- t i time. )
i% / 1
- 4. Utilize the Safeguards 4. NSS and Operations i equipment operability management will begin checklists. discus' sing use and extent of Safeguards equipment operability checklists.
i EXAMINER CUE: Inform I candidate that it is not ' necessary to determine which checklists will be , implemented for this JPM COMMENTS: Stop Time ir^x x Page 4 of 4 After Val
. . .. _ - - . . . . - ~ . . - - - - . . - . . .
- c .
I. Record Type #A9 3308
;7.
>.( DUQUESNE LIGHT COMPANY L Beaver Valley Power Station - l Unit 1/2
~
TINO 380 ONINIVH180d 1/2OM-48.1.H , r)I RESPONSE AND NOTIFICATION FOR A POTENTIAL-TAMPERING OR MISPOSITIONING EVENT Issue 4 Revision 0
~~
Prepared by Date Pages issued Effective Date J. G. Treese 07/10/97 H1 thru Hs AUG 081997 Reviewed by - Date Vahdated by Date M. Wahlenmayer 07/21/97 J. G. Treese 07/21/97
~
1 OSC Meeting No. Date Approved b Date BV-OSC-30-97 07/30/97 [ 7 37_;7) CONTROLLED MP3UNOT3
Beaver Valley Power Station Unit 1/2 1/2OM-48.1.H ,
, Conduct of Operations issue 4 Revision 0 t)' Organization and Responsibility of the O)erations Page H2 of 5 RESPONSE AND NOTIFICATION FOR A POTENTIAL TAMPERING OR MISPOSITIONING EVENT V. INSTRUCTIONS A. The administrative instructions to be followed upon discovery or notification of a potential tampering e mispositioning event are outlined below. As a minimum, a Condition Report should be written for all events which prompted utilization of this procedure.
Examples of items which may not have resulted in tampering or component - mispositioning, but should be considered for Security notifications are:
- 1. Bomb Threats
- 2. Attack Threats
- 3. Civil Disturbance
- 4. Discovery of a Breach of the Perimeter Barrier
- 5. Vital Area Found Unlocked and Unattended OR Vital Area Barrier Found Breached
- 6. Fire, Explosion or Other Catastrophe
- 7. Intemal Disturbance
- 8. Multiple Losses of either Onsite or Offsite Communications
(~') 9. Plant Penetrated ar< Held Hostage t/ 10. Personnel Held Hostage ( 1 11. Site Employee Strike Actions
- 12. Loss or Degradation of CNMT Intrusion Detection Systems
- 13. Confirmed tampering to Valve locking Mechanism (locking devices are: locks, hardened chains, light weight chains, and stainless steel cables. Ty-wrap is NOT considered a locking device.)
B. Dispatch an operator to the affected area to assess the potentici tampering or mispositioning and to limit access to the component. Instruct the operator to leave the equipment in the "AS-FOUND* condition, unless personnel safety concerns or plant operation warrant manipulation. C. Utilize Figure 48.1.H-1 to deterrnine appropriate level of required actions with regards to notification of plant personnel. The decisions require some judgment. Immediately notify Security Shift Supervisor and Operations Management if the event is determined to involve actual tampering or intentional mispositioning. D. Utilize the Safeguards Equipmant Operability Checklists if intentional mispositioning or tampering is identified. Operations management will determine the scope / extent of the performance of the respective checklists. E. Consideration should be given to the performance of the Safeguards Equipment Operability Checklists on the similar systems on the unaffected unit.
,r^w F. Provide notification to the Security Shift Supervisor after the completion of the initial ~j investigation if the event is not determined to involve tampering or intentional mispositioning:
1 1 \
m Beaver Valley Power Station Unit 1/2 1/2OM-48.1.H Conduct of Operations issue 4 Revision 0 Organization and Responsibility of the Operations Page H1 of 5 RESPONSE AND NOTIFICATION FOR A POTENTIAL TAMPERING OR MISPOSITIONING EVENT
- l. PURPOSE The purpose of this procedure is to provide administrative instructions regarding what constitutes a " tampering" event and what constitutes a valve or breaker "mispositioning" event. Guidance regarding the notifications of these events to plant security and management personnel is provided.
II. SCOPE instructions provide guidance to be followed from the time of discovery and/or notification of a " tampering" event or a valve or breaker "mispositioning" event, including notifications, reports and reviews necessary. Ill. DEFINITIONS A. Tamperina Event - an intentional or willful event that results in the alteration of a physical plant component or system which is detrimental to plant operation and/or safety. B. Mispositionina Event - the positioning of a valva or breaker out of its Operating Manual Section 3 Normal System Arrangement (NSA) position that is NOT the result of one of the following: 1) an approved procedure under the direction of the S, NSS/ANSG,2) documented by a Caution Tag,3) documented by an Equipment Clearance, and 4) documented in the " Daily Journal" as a component manipulation that is rdatively short, simple, routine, within the capability of the qualified individual and has been granted approval by the NSS/ANSS. C. Throttlina - the positioning of a valve from fully open to fully closed, as determined by a quantified system parameter being manito.ed (e.g., pressure, temperature, flbw) through the performance of an approved, controlled procedure, log or OM Section 3. IV. RESPONSIBILITIES A. The plant operators are responsible to notify the NSS/ANSS of the discovery of a tampering event or a valve / breaker mispositioning event, in accordance with this procedure. B. The NSS/ANSS are responsible for utilizing this procedure to determine the appropriate notifications / response to an event described by this procedure. O
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Beaver Vaiiey Power Station - Unit 1/2 1/20M-48.1.H
- n. Conduct of Operations issue 4 Revision 0
.,t Organization and Responsibility of the Operations Page H3 of 5 RESPONSE AND NOTIFICATION FOR A POTENTIAL TAMPERING OR MISPOSITIONING EVENT G. Refer to NPDAP 5.2," Initiation of Condition Reports', which provides the i a instructions for the admin. control and preparation of Condition Reports. .(. l l l i l . l l
i . l Unit 1/2 1/2OM-48.1.H Beaver Valley Power Station issue 4 Revision 0 Conduct of Operations Page H4 of 5 ,, Organidion and Responsibility of the Operations RESPONSE AND NOTIFICATION FOR A POTENTIAL TAMPERING OR MISPOSITIONING EVENT VI. REFERENCES A. Response to Notice of Violation EA 97-076, ND3NSM:7698 dated April 21,1997. B. NPDAP 5.1," Reporting Requirements". C. NPDAP 5.2," Initiation of Condition Reports". Vll. CHRONOLOGY OF CHANGES A. Revision 0 - new procedure. Vill. FIGURES A. 48.1.H-1, Mispositioning/ Tampering Guidelines (O ' I \ l l O
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-RTL #AS.635.J BVPS JOB PERFORMANCE MEASURE
, \j . Topic A.2 Surveillance Testing Question # 1 I
'The plant is in Mode 1, with All systems in NSA.
A PMP-is due to change the. fuel oil filter on the #2 Diesel. The PRA has been completed and the-risk is within acceptable limits. l The GMNO has approved the performance of this PMP.
~
l What SPECIFIC additional administrative actions are required to be performed as part of'the Clearance /Tagout to.' ensure operability of redundant train components. l l lp lV
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'RTL #A5.635.J BVPS JOB. PERFORMANCE MEASURE Topic A.2 Surveillance Testing
' Question # 1 The plant is in Mode 1, with All. systems in NSA.
A'PMP is due to. change the fuel oil filter on the #2 Diesel. The PRA has been completed and the risk.is within acceptable limits.. ~ Tho'GMNO has approved the performance of this PMP. What SPECIFIC additional administrative actions are required to be performed as part of the Clearance'/Tagout to ensure operability of redundant train components. s ANSWER: NOTE:
/'"i -This' question is surrounding the ESF checklist.
!( )L 1 The candidate.may' discuss numerous other administrative requirements.
- 1. Verify 2FWE*P22 operability.
. .2. Verify no thunderstorm or tornado watches.
- 3. Verify BOTH UNIT 1 D/Gs operable.
- 4. TS 3.8.1.1 actions completed within 1 hour PRIOR to removal.
TIME - 5' minutes ALLOTTED: k ,
.KSA #: 2.2.13 3.8 l
[ I NPDAP 3.4 attachment 5 item 8 page 3 rev. 9 REF: 4 i COMMENTS: l - jV-
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__' RTL #A5.635.J BVPS JOB PERFORMANCE MEASURE Topic A.2 Surveillance Testing Question # 2 The plant is operating at 100% power all systems in NSA except 2RCS*PT455 PZR Pressure transmitter has been OOS for the past 30 days. ALL Tech Spec required bistables have been placed in their tripped condition. I&C informs you that 2RCS*PT456 PZR Pressure transmitter was due for its functional testfMSP) 22.75 days ago. Brief1.y discuss what Tech spec actions will be required to perform the functional test for 2RCS*PT456 PZR - Pressure transmitter. Includc any applicable time limits. ANSWER: (per TS 3.0.6 and its bases) Under administrative control, the bistables for 2RCS*PT455 PZR Pressure transmitter may be untripped (to perform testing on 2RCS*PT456 PZR Pressyre transmitter). The allowable time for having the bistables for 2RCS*PT455 PZR Pressure fr x transmitter untripped MUST be limited to that I ) time ABSOLUTELY necessary to perform the testing. NOTE: The 30 days and 22.75 days in the question, are there to force the student to realize that the allowable 25% extension for the 92 day required frequency (23 days) for the functional testing is about to expire. TIME 10 minutes ALLOTTED: KSA #: 2.1.12 4.0 REF: Tech Spec 3.0.6 and bases COMMENTS:
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After Val
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i p RTL #AS.635.J .BVPS JOB PERFORMANCE MEASURE l Topic A.2 surveillance Testing l Question # 2 The plant is operating at 100% power all systems in NSA except 2RCS*PT455 PZR Pressure transmitter has been OOS for the past 30 days. ALL Tech Spec required bistables have been placed in their tripped condition. I&C informs you that 2RCS*PT456 PZR Pressure ' transraitter was due for its functional test (MSP) 22.75 days ago. Briefly discuss what Tech spec actions will be required to perform the functional test for 2RCS*PT456 PZR i Pressure transmitter. Include any applicable time limits. !% j l-i 1
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I i 1-l x 4 After Val
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l p_EAVER VALLEY JOB PERFORMANCE MEASURE l EVALUATOR COVER SHEET 4 JPM Number: ADM-PAR Rev: 0 System #: '4 . Faulted: k JPM
Title:
Determine PAR K/A
Reference:
2.4.44 / 4.4 Task ID #:3440240302 f x SRO ! JPM Designation: NO O RO JPM Application: E NRC X Initial Exam Training
, .. . , 9 Evaluation Method LOCATION TYPE l
X Perform Plant Site Training Simulate Simulator O Annual Requal. Exam
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f x Classroom OJT X Initial Operator. Exam I Administered By: Other: !. BV-T l 0 NRC Other: Evaluation Results Performer: Name: Employee No: b Results O SAT Time (minutes) ! UNSAT* Allotted: 15 Actual: l Time Critical: Yes @ No
- Comments (Required for UNSAT Evaluation):
f ' s j Evaluation Results Check here if same as above Observer 1: Name: Employee No: Observer 2: Name Employee No: Observer 3: Name Employee No: Observer 4: Name Employee No: Time (minutes) Results ~ Question ID Allotted Actual SAT UNSAT* Question #1 Employee No: Question #1 Employee No:
- Comments (Required for UNSAT I ation):
Evaluator (Print): Organization: Evaluator Signature Date: After Val
RTL #AS.635.J BEAVER VALLm JOB PERFORMANCE MEASURE CANDIDATE DIRECTION SHEET A
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- THIS SHEET TO BE GIVEN TO CANDIDATE Read:
Task: Determine PAR 25 minutes ago a LOCA occurred with a Loss of INITIAL Both AE and DF busses. Power to the Busses has CONDITIONS: NOT been restored. The following plant conditions - exist: o 8 hottest Core Exit TCs indicate 749 F. o Subcooling is -162 F. o RVLIS Full Range indicates 35%. (No RCPs running) o 150) wind direction is from 120' at . 15 MPH. o 500' wind direction is from 128a at 19 MPH. o Dose projectionc are not yet available, and are expected in about 30 minutes.
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INIT. CUE: You are the Emergency Director and the TSC/ EOF have not yet been activated. You are to evaluate i l the above conditions and determine which, if any, Offsite Protective Action Recommendations are necessary. l At this time, ask the evaluator any questions you have on this l JPM. When satisfied that you understand the assigned task, announce "I am now beginning the JPM". , Simulate performance or perform as directed the required task. Point to any indicator or component you verify or check and announce your observations. F.fter determining the Tack has been met, announce "I have completed the JPM". Then hand back this sheet to the evaluator.
,y i 1 After Val
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RIL #A5.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE EVALUATOR DIRECTION SHEET f~s
! 1 V JPM NUMBER: ADM-PAR JPM TITLE: Determine PAR ,
' TASK STAN.: Protr'tive Action Recommendations determined in accordance with EPP/IP 4.1 RECOMMENDED STARTING LOCATION: CONTROL ROOM DIRECTIONS: You are to simulate (perform) the task ,
Determine PAR. , INIT. CONDITIONS: 25 minutet ago a LOCA occurred with a Loss of Both AE .nd DF busses. Power to the Busses has NOT been restored. The following plant conditions exist: o 8 hottest Core Exit TCs indicate 749'F. o Subcooling is -162 F. o RVLIS Full Range indicates 35%.
- l (/~'\ ) (No RCPs running) o 150' wind direction is from 120a at 15 MPH. i o 500' wind direction is from 128o at i 19 MPH. )
O Dose projections are not'yet available, -l and are expected in about 30 minutes. l INIT. CUE: You are the Emergency Director and the TSC/ EOF have not yet been activated. You l are to evaluate the above conditions and j determine which, if any, Offsite Protective , f Action Recommendations are necessary. ! I
REFERENCES:
EPP/IP 4.1 Rev. 9 I p TOOLS: NONE HANDOUT: NONE (EPP and EPP/IPs are.to be made available to candidate.) , ( v After Val 4
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RTL #AS.635.J h
) NUMBER- TITLE mA~
ADM-PAR Determine PAR l' STEP STANDARD (Indicate "S" for Sat. or "U"
'("C" denotes critical step) for Unsat.)
START TIME: __ . EVALUATOR NOTE: The candidate may begin by determining Critical Safety Function status or by evaluating event - classification prior.to referencing EPP/IP 4.1 q_ 1. Review EPP/IP 4.1. 1.1 Candidate locates 'I \ EPP/IP 4.1. N-s l 1.2 Candidate determines that Protective Action i Recommendations required within 15 l_ ' minutes if' General ' Emergency 1.s declared. ) l l l COMMENTS: . 1
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o Page 1 of 4 After Val
RTL #AS.635.J f% . - NUMBER TITLE ADM-PAR Determine PAR STEP STANDARD (Indicate "S" for Sat. or "U' ("C" denotes critical step) for Unsat.) 2.2 Candidate determines a . General Emergency condition. EVALUATOR NOTE: TAB 3.1 is expected classification. Others may also apply. EVALUATOR NOTE: Candidate may
.rg reference EOPs to determine the CSF Red Path conditions
'( ) 'b exist. COMMENTS: 3.' Candidate refers to 3.1 Candidate enters Offsite Protection Offsite Protective-Action Action - Recommendation. Flow Recommendation Chart. Flowchart oh General Emergency EAL other than
7.1. COMMENTS
V Page 2 of 4 After Val
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-RTL #A5.635.J:
~\ /9
) NUMBER TITLE ADM-PAR Determine PAR STEP- STANDARD (Iridicate "S" for Sat. or "U"
("C". denotes critical step) for Unsat.)
- 4. Reference' Attachment 4.1 Candidate 2 and Determine references Table 1 Downwind Wedge. to determine that the 150' elevation Downwind Sectors are MNPQR.
4.2 Candidate references Table 1 to determine that the 500' elevation (,) Downwind Sectors are NPQRA.*. J COMMENTS: 5.C Determine Offsite 5.1.C Candidate determines ' Protective Action the following Protective ! Recommendation. Action Recommendation: ! Evacuate 360 for two miles. - Evacuate Sectors MNPQRA for five miles. Shelter remainder
. of 10 mile EPZ.
'm.
I Q(. COMMENTS: i' Page.3 of 4 After Val
-RTL #AS.635.J jr):
i L /' i NUMBER TITLE ADM-PAR Determine PAR STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes' critical step) for Unsat.)
- 6. Report JPM 6.1 Candidate reports completion. that the JPM is complete.
3 COMMENTS: S . . /'~d '( STOP TIME
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EPP/IP 4.1 A1.002L , u[ g - l
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OFFSITE PROTECTIVE ACTIONS l ft 1 l 1 l FOR TRAINlhG USE ONLY,
. . - . . . . . l Rev.9
EPPilmplementing Procedure EPP/IP 4.1 7 . A1.002L
! ) OFFSITE PROTECTIVE ACTIONS A_/
APPROVAL PAGE Intent Related Revision Yes X No IF YES OSC and Site Approval - OSC Meeting Number Date A NOTE: The approval of this revision by the Onsite Safety Committee ensures the requirements of 10 CFR 50.54(q) have been considered and not compromised. Reviewed Director, Emergency Preparedness Date 7N i i As Approved Manager, Management Se' - Date IF NO l Reviewed I /2 7/97 Director, Emergency Preparedness Date , L Approved _ - ta- /2[z2[97
- l. Manager, Management Services Date l-
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, .. l EPP Implementing Procedure EPP/IP 4.1 ;
f OFFSITE PROTECTIVE ACTIONS , 1 i EFFECTIVE INDEX Issue 8 Rev. ~ 0 OSC Approved 3-12-87
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Issue 9 Rev. O Non-Intent Related 10-9-90 l 1 Non-Intent Revision 11-19-91 2 Non-Intent Revision 12-29-92 Rev.- 5 OSC Approved 11-10-93 6 Non-Intent Revision 11-15-94 l 7 Non-Intent Revision 10-23-96 ( 8 Non-Intent Revision 6-17-97 I(' 9 Non-Intent Revision 1-1-98 J
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a { EPP/ Implementing Procedure EPP/IP 4.1 OFFSITE PROTECTIVE ACTIONS 1 O-F TABI.E OF CONTENTS A. Purpose e B. References C. Responsibilities
- D. Action I2Vels/ Precautions
. E. Procedure F. Final Condition G. Attachments O
I O 6 Ue Dec 0
EPP/Implem:nting Procedure EPP/IP 4.1 [ OFFSITE PROTECTIVE ACTIONS O A. PURPOSE This procedure provides guidance to the Emergency Director / Emergency Recovery Manager for the recommending of offsite protective actions to State and/or County emergency services groups. The Beaver Valley Power Station is required to make recommendations for protective actions as part of the initial notification or follow-up process if the nature and magnitude of the actual or potential radioactivity release warrants protective actions for the public. B. REFERFNCES-1.0 Beaver Valley Power Station Emergency Preparedness Plan and Implementing Procedures. 2.0 USEPA 520/8-75-001 (and subsequent revisions) " Manual of Protective Action Guides and Protective Actions for Nuclear Incidents". 3.0 USEPA 570/9-75-003 " National Interim Primary Drinking Water Regulations". (
)
7 v' 4.0 County and State Emergency Plans. 5.0 Title 10 Code of Federal Regulations Part 50, Appendix E. 6.0 NUREG-0654/ FEMA-REP-1 " Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants." 7.0 ERS-SFL-84-009, " Radiation Monitor Decision 12vels For EPP". 8.0 ERS-SFL-86-007, "EPP/IP 4.1 PAG Decisions". 9.0 NRC Response Technical Manual - 92 Vol.1, Rev. 2. 10.0 EPA Manual of Protective Actica Guides and Protective Actions For Nuclear Incidents (EPA 400-R-92-001). I l
! l 1 Rev. 9
EPP/IP 4.1 EPP/ Implementing Procedure OFFSITE PROTECTIVE ACTIONS C. RESPONSIBILITIIM 1.0 The Emr ancy Director and the Emergency Recovery Manager are the only positions mthorized to recommend offsite protective actions on behalf of Duquesne Light Company. 2.0 In the event protective action decisions are necessary prior to the activation of the Technical Support Center, the onduty Nuclear Shift Supervisor, in his role as Emergency Director, will determine a Protective Acdon Recommendation, using Attachment 1 of this procedure, considering plant systems status information from shift personnel and dose projection information from the Radiation Technician (or Health Physics Supeivision). 3.0 When the Technical Support Center is activated, responsibility for protective action recommendations shifts from the Nuclear Shift Supervisor to the Technical Support Center Emergency Director. 4.0 When the Emergency Operations Facility is activazd, responsibility for r protective action recommendations shifts to the Emergency Recovery Manager with input from the Emergency Director. 5.0 The development of a Duquesne Light Company Protective Action Recommendation requires input from different individuals within the Beaver Valley emerger.cy response orgamzation. The Emergency Director / Emergency Recovery Manager may solicit input from the personnel identified below, and/or, from appropriate representatives of the three State govemments and the NRC in arriving at his decision. Once the Emergency Director / Emergency Recovery Manager has decided upon a recommendation, it may be relayed to the offsite agencies by designated DLC emergency response personnel. 6.0 When the TSC (and/or EOF) is activated, designated EA & DP personnel will perform radiological assessments, will evaluate the need for offsite protective actions based on these assessments, and will provide appropriate recommendations to the Emergency Director / Emergency Recovery Manager for his consideration. EA & DP personnel will use the EPP/IP 2 series for these determinations. O i l 2 Rev.9
. l EPP/Impicmenting Procedure EPP/U' 4.1 I OFFSITE PROTECTIVE ACTIONS lQ)
D. ACTION LEVELS / PRECAUTIONS 1.0 PROTECTIVE ACTION GUIDES - AIRBORNE RELEASF3 NOTE: i If there are simultaneous accidents at BV-1 and BV-2 resulting in release (s) to j the environment, dose projections will be required for both units. When ! determining the utilities' Protective Action Recomme ttions (PAR) under I this condition, the PAR must be predicated on the bas the total dose from both units. l 1.1 The Protective Action Recommendation is based on Attachment 1. 1 1.2 Based on dose assessmen s. Do Protective action should be recommended for incidents involving actual or potential airborne teleases of radioactive material which are projected to result in doses to members of the general p public that are less than 1 rem to the whole body (TEDE) or 5 rem to the
/ child thyroid (CDE).
HOWEVER, a Protective Action Recommendation may be required due to operational conditions. 1.3 Sheltering or evacuation of members of the general public within the affected area shall be recommended for incidents involving actual or potential airborne releases of radioactive material which are projected to result be doses to members of the general public, greater than or equal to I rem to the whole body (TEDE) or 5 rem to the child thyroid (CDE). 1.4 Attachment 1 (Offsite Protective Action Recommendation Flowchart) is used to determine the need for making a protective action recommendation based on an analysis of the fission product barriers via the Critical Safety Functions and/or dose projections. 1.5 u -d above, protective action decisions are primarily based on plant ,[ - i status assessments, and secondarily based on dose projections. L time and personnel availability permit, these two types of assessments may be performed simultaneously, and the results of both included in the protective action decision. Any upgrade to the protective action k recommendation will be based on dose projections / assessments. i 3 Rev.9 l
EPP/IP 4.1 EPP/ Implementing Procedure OFFSITE PROTECTIVE ACTIONS NOTE: The BVPS Emergency Response Organization makes every attempt to relay the utilities Protective Action Recommendation as quickly as possible. The Gold Phone is the primary means of relaying the recommendation for onshift personnel. The Gold Executive Conference (GEC) is the primary means of relaying the recommendation for TSC/ EOF personnel.. This method provides a way of receiving immediate confirmation that the appropriate States and Counties fully understand the recommendation. The States and Counties also receive the recommendation via commercial phone line as desenbed in Step E.1.6 or E.2.7. This step ensures documentation is properly completed and serves as a backup to the GEC. 2.0 PROTECTIVE ACTION GUIDES - WATERBORNE RELEASES l 2.1 Recommendations shall be made to downstream water treatment plants (per EPP/IP 1.1, Attachment 2) to secure taking water from the Ohio River for liquid releases projected to exceed the concentration of radionuclide that will cause a dose commitment to any organ of 48 mrem. This is equivalent to 12 times the EPA Primary Drinking Water Standard, as measured at the water treatment plant discharge (to the
/
public distribution system). This is determined in accordance with EPP/IP 2.7, " Liquid Release Estimate" or EPP/IP 2.7.1, " Liquid Release Estimate - Computer Method". 3.0 IDENTIFICATION OF AFFECTED AREAS
. 3.1 The affected area will resemble a keyhole consisting of a circle with a 90 degree (or larger) wedge shaped sector attached in the downwind direction or depending on meteorological conditions, a circle with no downwind wedge (Attachment 2).
3.2 Attachment 2 and 3 provides the BVPS method for establishing the affected area. 3.3 When using dose projections as a basis for recommending offsite protective actions, projected doses calculated:
- r.t the EAB apply to the 0-2 mile radial circle;
- at 2 miles apply to the 2-5 mile downwind wedge or radial circle and; at 5 miles apply to the 5-10 mile downwind wedge or radial O
circle. 4 Rev.9
EPP/ Implementing Procedure EPP/IP 4.1
! OFFSITE PROTECTIVE ACTIONS
.. \. E. PROCEDURE 1.0 TSC/ EOF NOT ACTIVATED -- ACTIONS BY EMERGENCY DIRECTOR FOR AIRBORNE RELEASE NOTE: l Upon declaration of a General Emergency, a Protective Action Recommendation must be provided to the State / County Agencies within 15 minutes of the declaration. This information must also be provided on the Initial Notification Form. The steps which follrw are performed by the Emergency Director or by his designees. Recommendations by designees will be reviewed and approved by the Emergency Director. 1.1 Enter Attachment I with information obtained from shift personnel. 1.2 Determine from meteorological parameters, the plume direction and ; wind speed.
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1.3 Assess plant parameters to identify or estimate how long the release will continue. If the release has not started yet, estimate when the release will start and how long :t will continue, if possible. NOTE: If dose projections are not immediately available, provide the minimum Protective Action Recommendation per Attachment 1, and go to Step 1.6. 1.4 Obtain dose projection data from the Radiation Technician or Health - Physics Supervision determined in accordance with EPP/IP 2.6,
" Environmental Assessment and Dose Projection Controlling Procedure" and its supporting procedures. Do not delay recommending protective actions to wait for offsite monitoring team results. The projected dose for the Exclusion Area Boundary (EAB) should be calculated first, and l as necessary, for other distances.
1.5 Upgrade the initial protective action recommendation based on dose
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i \s' projections as necessary (refer to Step E.4.0). J l I I-l 5 Rev.9 l
EPP/IP 4.1 EPP/hnplementing Procedure OFFSITE PROTECTIVE ACTIONS 1.6 Direct the Communications and Records Coordinator (or other shift personnel) to document the recommendation on the appropriate Initial or to make Follow-up Notification Fonn (if upgraded) and recommendations to the appropriate onsite personnel and/or offsite authorities in accordance with Attachment 5 of this procedure and EPP/IP 1.1, " Notifications. f ACTIVATED -- ACTION BY EMERGENCY 2.0 TSC/ EOF DIRECTOR / EMERGENCY RECOVERY MANAGER FOR AIRBORNE RELEASE NOTE: Upon declaration of a General Emergency, a Protective Action Recommendation must be provided to the State / County Agencies within 15 minutes of the declaration. This information must also be provided on the Initial Notification Form. The steps which follow are performed by the Emergency Director until such time as the EOF is activated, after which, the steps are performed by the Emergency Recovery Manager or by their ( designees. Recommendations by designees will be reviewed and approved by the Emergency Director / Emergency Recovery Manager (ED/ERM). 2.1 Instruct the Assistant to the Emergency Recovery Manager to activate the Gold Executive Conference (GEC) Attachment 4, and inform the ED/ERM when it is activated. 2.2 TSC personnel will evaluate plant systems status, and provide information to the Emergency Director. The Emergency Director (Emergency Recovery Manager when activated) will develop Protective Action Recommendations considering plant systems status assessments in conjunction with Attachment 1. NOTE: If dose projections are not immediately available, provide the minimum Protective Action Recommendation per Attachment 1, and go to Step 2.5. 9 l l 6 Rev.9
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, EPP/ Implementing Procedure EPP/IP 4.1 O OFFSITE PROTECTIVE ACTIONS V
' 2.3 Direct EA & DP personnel to perform radiological assessments and determine forecast meteorological conditions in conjunction - with appropriate EPP/IP 2 Series procedures. EA & DP personnel are expected to evaluate poteatial ground contamination from plume fallout _,
and to make appropriate secommendations for reducing exposure from this - source. (Refer 9 EPP/IP- 2.6.10, " Ground Contamination
' Assessment and Protective Actions).
2.4 -Review the recommendations developed % the TSC and EA & DP personriel, 2.5' As time permits, the ED/ERM should discuss the Company recommendation with the three State agencies and with the NRC with the objective of obtaining a consensus recommendation, if possible. These discussions may occur in the EOF or by teleconferences (via the GEC or other communication' links, if necessary). In the absence of an agreement, the DLC recommendation shall be based on the BVPS staff's best evaluation of the plant conditions or dose assessment information. rk 2.6 If the minimum recommendation is being provided, go to Step 2.7. If dose projections indicate upgrading the recommendation, refer to Step E.4.0. 2.7 Direct the Communications and Records Coordinator.to' document the recommendation on the appropriate Initial or Follow-up Notification Form (if upgraded) and to make recommendations to the appropriate onsite personnel and/or offsite authorities in accordance with EPP/IP 1.1, " Notifications". 2.8 Notify DLC Nuclear Communications personnel of the recommendation, but direct them not to include the content of the Company's , recommendation in any news announcements. Such releases should only indicate that DLC has made a recommendation to offsite authorities and that these agencies are - considering the recommendation. This prohibition is intended to prevent confusion that might result if the action implemented differs from that recommended by DLC. -u 7 Rev.9
EPP/ Implementing Procedure EPP/IP 4.1 OFFSITE PROTECTIVE ACTIONS 3.0 WATERBORNE RELEASE 3.1 Obtain data in accordance with EPP/IP 2.7, " Liquid Release Estimate" or EPP/IP 2.7.1, " Liquid Release Estimate - Computer Method". 3.2 Per dose projections, for liquid releases corresponding to > 12 times EPA MPC, notify the Midland Water Treatment Plant (per EPP/IP 1.1, ! Attachn.ent 2) and recommend the Plant stop taking water from the Ohio l River until notified by the DEP/BRP. 3.3 If actual sample analyses at Midland indicates activity in excess of EPA , limits, additional sampling should be performed at East Liverpool, Ohio, l and Chester, WV and a similar recommendation made for these Plants. ) The Ohio EPA will determine when East Liverpool can resume taking i water from the Ohio River, and the WV Bureau of Public Health will { determine when Chester can resume taking water from the Ohio River. j l 3.4 Notify additional offsite authorities including the Coast Guard and the l US Corp. of Engineers per EPP/IP 1.1, Attachnient 2. ( i 4.0 UPGRADING PROTECTIVE ACTION RECOMMENDATIONS i 1 i NOTE: l l The initial Protective Action Recommendation is based on operational ! assessments. Any upgrades to the Recommendation will be based on dose ) projections exceeding the EPA PAG's at greater than 2 miles. l 4.1 Dose assessments should be perforined ir 7 junction with operational assessments, if possible. 4.2 A Protective Action Recommendation developed on the basis of i operational assessments (Attachment 1) is the minimum initial l recommendation and shall be instituted immediately, unless: I available dose projections indicate a more restrictive Protective Action Recommendation (e.g.: dose projection at 2 miles exceeds the EPA PAG's) or, the release has not started, the start time is not known AND the meteorological forecast for a consistent wind direction is not known. In this case the determination of a " downwind wedge" is meaningless 8 Rev.9
EPP/ Implementing Procedure EPP/IP 4.1 "D' OFFSITE PROTECTIVE ACTIONS since the wind direction may change prior to the release. (Example: ; For the evacuate 2 mile, 360* and 5 mile downwind wedge for this condition, a Protective Action Recommendation of 0-5 mile evacuation,360 degrees would be required.) Refer to Attachment 2.
' 4.3 In the event that EA&DP dose projections indicate an upgrade of the Protective Action Recommendation from Attachment 1 (i.e.: dose projections at 2 miles exceed the EPA . PAG's, etc.), the Emergency Director (Emergency Recovery Manager, if activated) shall discuss the upgraded Protective Action Recommendation, and its dose projection )
basis, with the three State agencies and with the NRC with the objective j of obtainmg a consensus recommendation, if possible. These discussions ! may occur in the EOF or by teleconferences (via the GEC or other I communication links, if necessary). In the absence of an agreement, the DLC recommendation shall be based on the BVPS staff's best evaluation of the plant conditions or dose assessment information. O 4.4- Direct the Communications and Records Coordinator to document the h recommendation on the appropriate Initial or Follow-up Notification Form (if upgraded Recommendation) and to make recommendations to the appropriate onsite personnel and/or offsite authorities in accordance
' with EPP/IP 1.1, " Notifications".
1-F. - FINAL CONDITIONS 1.0 All appropriate agencies have been notified of the Duquesne Light Company Offsite Protective Action Recommendation.
- . 2.0 The Gold Phone /GEC has been relinquished to the State and County agencies l
for coordination of siren activation or other discussions. I' 3.0 The emergency condition has been terminated and recovery has begun. 4.0 All Emergency Termination Notifications per EPP/IP 1.1 have been completed. G. ATTACHMENTS
' l.0 OFFSITE PROTECTIVE ACTION RECOMMENDATION FLOWCHART 2 2.0 DETERMINING PROTECTIVE ACTION DOWNWIND WEDGE 3.0 DOWNWIND AFFECTED AREA DECISIONAL AID (Reproduction)
'4.0 ACTIVATION OF THE GOLD EXECUTIVE CONFERENCE CALL 5.0 GOLD PHONE PROTOCOL 9 Rev.9
EPP/ Implementing Procedure EPP/IP 4.1 OFFSITE PROTECTIVE ACTIONS l j l I INTENTIONALLY BLANK O 1 e l 10 Rev.9
I t EPP/Impicmenting Procedures EPP/IP 4.1
.OFFSITE PROTECTIVE ACTIONS a TTACIIMENT 1 (1 of 1)
(v) OFFSITE PROTECTIVE ACTION RECOMMENDATION FLOWCIIART START EVACUATE 2 mile,360* and 5 mito downwind wedge GENERAL yot and EMERGENCY SHELTER remainder of 10 Based on EAL _ mile EPZ Other Than 7.1 (seanote t.2) No Y Continue Assessment. Expand the affected area if subse-s
' quent assessments, including the result *. of field measure-mei.ts, indicates the need.
k EVACUATE 2 mile,360* and I 10 mile downwbd wedge . I and 1 SHELTER remainder of 10 ! I mile EPZ l Projected Dose (8" N#* #*81 l p at 5 miles >1 yo3
) rem TEDE )
k_/ or ,,,,,,,, 1 Thy old DE No EVACUATE 2 mile,360* and 5 mile downwind wedge ; and ! SHELTER remainder of to I mile EPZ Projected Dose (8** "#* # 81 at 2 miles >1 y,s rom TEDE Or -
>5 rem Thyroid CDE No EVACUATE 2 mile,360*
and SHELTER remainder of to mile EPZ (see Note 3)
- 1. Minimum recommendation. If dose assessments have been completed by the time that this decision is made and a larger affected area is indicated, then the larger recommendation shall be made. Do not delay recom-mondation to await dose projection results.
.( A Rolor to Attachrnont 2 to define downwind wed;a
~~~J
- 3. If (1) the roloase has already started (or is expectod to start within ono hour) and (2) the projected release duration is projected to be loss than ono hour, recommend SHELTER for the 10 mile EPZ. If the projocted dose is greater than to rom TEDE or if the duration and start timos can not be reasonably determinod, the EVACUATION rocommendation spocifiod above shall be mado.
AIPAGCHfPM 11 ReV 9
EPP/Impicmenting Procedures EPP/IP 4.1 OFFSITE PROTECTIVE ACTIONS l i INTENTIONALLY BLANK O l i O 12 Rev.9 1
EPP/ Implementing Procedures EPP/IP 4.1 iO] ,! OFFSITE PROTECTIVE ACTIONS ATTACIIMENT 2 (1 of 2) DETERMINING PROTECTIVE ACTION DOWNWIND WEDGE
- 1. Determining Affected Downwind Sectors l NOTE:
l The instructions below describe the use of Table 1. The decisional aid shown on I Attachment 3 may be used instead of the table. In the latter case, return to Step 1.5 below. 1.1 Obtain the 150' and 500' elevation wind directions from an ARERAS terminal or from other sources as described in EPP/IP 2.6.5. 1.2 Using the 150' elevation wind direction and Table 1, identify the downwind sectors. 1.3 Using the 500' elevation wind direction and Table 1, identify the downwind sectors. kJ 1.4 The downwind wedge is all of the sectors identified in Steps 1.2 and 1.3, and I any sectors bracketed by the identified sectors (i.e., upper and lower wedges do not overlap). 1.5 If the difference between the two wind directions is between 165 and 195 degrees, include all sectors in the recommendation. NOTE: Step 1.6 does NOT apply to the minimum recommendation associated with severe core damage or loss of control. 1.6 If it is likely that a change in the wind direction greater than one sector will occur prior to or during the release transport through the 10-mile EPZ, expand the down wind wedge to a full 360 degrees. Such conditions should be assumed based on the following: 1.6.1 (TSC/ EOF only) Weather forecast obtained from NWS indicate weather l front will pass thru EPZ during release transport. ! 7N, I! V~ 1.6.2 Variable wind direction associated'with low wind speeds (i.e.,0-2 mph). l 1.6.3 Release transport will span sunrise or sunset hours. 13 Rev.9
EPP/ Implementing Procedures EPP/IP 4.1 OFFSITE PROTECTIVE ACTIONS ATTACHMENT 2 (2 of 2) DETERMINING PROTECTIVE ACTION DOWNWIND WEDGE 1.6.4 Release has not started and start time cannot be estimated with certainty. Table 1 Wind Direction From Downwind Sector Rance Sectors A 350 - 11 GHJKL B 12 - 34 IUKLM C 35 - 56 JKLMN D 57 - 79 KLMNP E 80 - 101 LMNPQ F 102 - 124 MNPQR G 125 - 146 NPQRA H 147 - 169 PQRAB J 170 - 191 QRABC K 192 - 214 RABCD L 215 - 236 ABCDE M 237 - 259 BCDEF [ N 260 - 281 CDEFG l P 282 - 304 DEFGH Q 305 - 326 EFGHJ R 327 - 349 FGHJK l l l 9 l 14 Rev.9 l 1
. EPP/ Implementing Procedures EPP/IP 4.1 OFFSITE PROTECTIVE ACTIO'NS ATTACIIMENT 3 (1 of 1)
DOWNWIND AFFECTED AREA DECISIONAL AID Rotate plastic disk R \^fB
- to align arrow with 150' 1
no 2.s is r so g wind direction as indicated on meteorological mstruments . 3,,
.P{M
~
/
(direction from which wind is p uo af a Q coming.) f.p]'3' ('r .
~ '" fjklff k;f w: ,.s l' '
N m:}@. M $ # N...
$:. E
- ., I.! f dg[5,, ~
l (1 M e
..rgy ..
;... F Rotate plastic disk to 2 m N ', , ,,,
align arrow with 500' wind ' direction
- as indicated on meteorological instruments
[ ' ' ' ,#,, , i ,'* _ Q (direction from which wind is coming.) , KfJ\H 3 Identify affected sectors. In this example: B through L. If . smaller in:luded wedge (as shown above) exceeds about 75 degrees, al! sectors should be included in recommendation. If the outer edge of a wedge bisects a sector, include the entire sectx in the recornmendation. The protective action recommendation for the 0-2 mile radies will be all sectors (A-R). The affected sectors identified with this tool apply beyono 2 miles. From MIDAS terminal or Met. Shel:er (150' wi;l direction is used in lieu of ground level wind
- direction to avoid interference from terrain adjacent to meteorological tower.)
1:; Rev.9
I 1 I EPP/ Implementing Procedures EPP/IP 4.1 OFFSITE PROTER FIVE ACTIONS i 1 l I 1 t INTENTIONALLY BLANK { 9 16 Rev.9
EPP/ Implementing Procedures EPP/IP 4.1 A5.715FZ ( OFFSITE PROTECTIVE ACTIONS ATI'ACIIMENT 4 (1 of 2)
.%)
ACTIVATION OF THE GOLD EXECUTIVE CONFERENCE CALL NOTE: The Gold Executive Conference (GEC) is a function of the Beaver Valley Emergency Response System (BVERS). The GEC is the method that the On-Call Emergency Response Orgamzation (ERO), particularly the Emergency Director, or Emergency / Recovery Manager if activated, shall use to . establish a conference call for the purpose of discussing a Protective Action Recommendation (PAR) with the Ofrs ite Agencies. This call shall be initiated by the Assistant to the E/RM. NOTE: This procedure should be implemented prior to, or in anticipation of, a General Emergency declaration to ensure timely discussion of plant conditions with the State and County agencies. f3 1) Obtain the PASSCODE and SCENARIO NUMBER envelop from the EOF Emergency jy Cabinet to activate the Gold Executive Conference (GEC) call. l.
- 2) From a touch tone phone dial 393-4370 (PAX 4370) to access the Beaver Valley Emergency Response System (BVERS).
2.1 If GEC is unavailable, go to Step 12.
- 3) At the beginning of the message, interrupt the message by entering PASSCODE #1.
- 4) When prompted, enter the SCENARIO NUMBER.
'5) a) When prompted, verify scenario number by pressing "9" for YES OR "6" for NO. _
b) When prompted "You are about to que scenario number "XXXXX" Do you wish to initiate scenario number "XXXXX"?", enter "9" for YES OR "6" for NO.
- 6) Hang up.
A NOTE:
) You must dial the prefix "9" or "#9" to obtain an outside line to enter the GEC call. This number is NOT a PAX extension.
17 Rev. 9
EPP/ Implementing Procedures EPP/IP 4.1 A5.715F2 OFFSITE PROTECTIVE ACTIONS ATTACIIMENT 4 (2 of 2) ACTIVATION OF THE GOLD EXECUTIVE CONFERENCE CALL From a touch tone phone dial "9-393-1900" When prompted, enter PASSCODE #2 7) followed by the "#" sign.
- 8) Confirm that the following Offsite Agencies are on the Conference call:
BCEMA CCEMA HCOES PEMA OEMA WVOES DEP/BRP NOTE: Any person disconnected, or any additional personnel, may enter the GEC at any time, once the system is activated, by dialing 393-1900 and providing the GEC PASSCODE.
- 9) If an Offsite Agency does not respond, call the agency using the contact phone number from EPP/IP 1.1," Notifications", and request they call into the GEC by dialing 393-1900 and providing the GEC PASSCODE.
- 10) The Assistant to the E/RM shall then turnover the phone to the ED, or E/RM if activated, to provide the PAR.
I1) Upon providing the PAR, the ED, or E/RM if activated, shall answer ar y questions from the Offsite Agencies then turn over command of the GEC to the Offsite Agencies for discussions and siren coordination.
- 12) If GEC is unavailable, utilize commercial lines.
12.1 Contact the State / County agencies per EPP/IP 1.1 " Notifications", Attachment 2 and provide the PAR. 12.2 PA DEP/BRP may be contacted using the " Blue" Hotline in the EOF.
- 13) If commercial phone systems are unavailable, the DLC Radio System is the alternate method for providing the PARS to the Counties. EPP/IP 1.2, Attachment 3 (Step 6.0) provides direction for using the radio system. The Counties should then contact their respective States.
18 Rev.9
.. . .- - _. ._. = -. .
EPP/ Implementing Procedures EPP/IP 4.1 m
-( ) OFFSITE PROTECTIVE ACTIONS v
A'ITACIIMENT 5 (1 of 7) GOLD PHONE PROTOCOL A. PURPOSE This _ attachment provides instructions and protocol for the use of the Emergency i Communication System (Gold Phone) for both onsite and offsite personnel during emergency situations. B. RESPONSIBILITY The Emergency Director is responsible to ensure the actions outlined in this attachment are completed onsite. C. FUNCTIONS 1.0 Onsite 'U !/ 1.1 The Gold Phone has been designated as the primary means for onshift utility personnel to relay their Protective Action Recommendation to the State and County agencies. 1.2 The Gold Phone may also be used in emergency situations as a means for upper level management discussions and conference calls as initiated l by the utility. l 2.0 Offsite 2.1 The Gold Phone is the means for the States (PA, Ohio and W. Va.) and l- the Counties (Beaver, Columbiana and Hancock) to receive the utility's L Protective Action Recommendation. 2.2 The States, once an Executive decision is made, may use the Gold Phone to relay the official Protective Action Recommendation to the applicable County. 2.3 Once the Counties have received the PAR from their States, they may use the Gold Phone to coordinate the siren activation. LJ 19 Rev.9
L EPP/ Implementing Procedures EPP/IP 4.1 OFFSITE PROTECTIVE ACTIONS ATI'ACIIMENT 5 (2 of 7) GOLD PHONE PROTOCOL D. PROCEDURE 1.0 Control Room; Fast-breaking Accident (Daylight Working Hours) 1.1 Should a fast-breaking accident resulting . a General Emergency and a Protective Action Recommendation (PAT.) occur during normal working hours, the following steps should be per'ormed: NOTE: All actions associated with step 1.1.1, 1.1.2, and 1.1.3 should be documented, and conducted within 15 minutes of the General Emergency Declaration. NOTE: PEMA can no longer be contacted via the Gold Phone. PARS must be relayed via telephone at (717) 651-2001. 1.1.1 The ED (NSS) should instruct the Communications and Records Coordinator (C&RC) to activate the Gold Phone (press "= 99"), conduct a role call of all groups and relay the information from the Initial Notification Form (per pages 5, 6 and 7 of this Attachment). 1.1.2 Once the C&RC arrives at the Protective Action Recommendation section, he should preface the PAR by stating that the following is the utilities PAR as determined by (give ED's name). l l. O i l 20 Rev. 9
EPP/Impicmenting Procedures EPP/IP 4.1
/'N.
OFFSITE PROTECTIVE ACTIONS (] ATTACHMENT 5 (3 of 7) GOLD PHONE PROTOCOL NOTE: Upon receiving the PAR from the utility, the offsite agency representative may wish to speak with the ED. Every effort should be made to meet this request. 1.1.3 Those not answering the Gold P' hone and receiving the Initial Notification and PAR must be contacted via the commercial phone line. During the subsequent conversations, these agencies , should be informed that the PAR has already been relayed to various agencies (specify which agencies). NOTE: the PAR must be relayed by the Emergency Director. 1.1.4 After all offsite agency questions are addressed, the Gold Phone e may be used by the States and Counties to coordinate their response actions. ((' 2.0 Control Room; Fast-breaking Accident (Non-daylight Hours) 2.1 Should a fast-breaking accident resulting in a General Emergency and a Protective Action Recommendation (PAR) occur during non-daylight hours, the following steps should be performed: NOTE: Actions performed in steps 2.1.1, 2.1.2 and 2.1.3 must be documented, y and conducted within 15 minutes of the General Emergency Declaration. NOTE: PEMA can no longer be contacted via the Gold Phone. PARS must be relayed via telephone at (717) 651-2001. C't
,G i
21 Rev.9
EPP/ Implementing Procedures EPP/IP 4.1 OFFSITE PROTECTIVE ACTIONS ATI'ACIIMENT 5 (4 of 7) GOLD PIIONE PROTOCOL 2.1.1 The ED (NSS) should instruct the C&RC to activate the Gold Phone (press "* 99", conduct a role call of all groups and relay the Initial Notification information (per pages 5, 6 and 7 of this Attachment). However, limited offsite agency response should be expected (States' response centers not manned 24 hours, while Counties will respond). 2.1.2 The C&RC should relay Initial Notification information and the utilities PAR to those agencies responding to the Gold Phone. The PAR should be prefaced by stating that the following is the utilities' PAR as determined by the ED (give. name). NOTE: Upon receiving the PAR from the utility, the offsite agency representative may wish to speak with the ED. Every effort should be made to meet this request. ( 2.1.3 Those not answering the Gold Phone and receiving the Initial Nodfication and PAR mug be contacted via the commercial phone line. During the subsequent conversations, these agencies should be informed that the PAR has already been relayed to various agencies (specify which agencies). NOTE: the PAR must be relayed by the Emergency Director. 2.1.4 After all offsite agency questions are addressed, the Gold Phone may be used by the States and Counties to coordinate their response actions. _ O 22 Rey,9
- EPP/Impicmeating Procedures EPP/IP 4.1 A5.715FZ OFFSITE PROTECTIVE ACTIONS ATTACHMENT 5 (5 of 7) v GOLD PHONE PROTOCOL E. GOLD PHONE PROTOCOL The protocol established in this attachment applies only to emergency situations and Beaver Valley Power Station drills and exercises. During these situations, an emergency communicator from the DLC Emergency Response Organization will be assigned to monitor this command line.
GOLD PHONE PROTOCOL CHECKLIST 1.0 The DLC emergency communicator will announce that the utility is ready to make a PAR and request control of the line. BVPS communicator: "This is the Beavi Valley Power Station requesting control of the Gold Phone. Please terminate all conversations at this time and respond to the following roll call." [ 2.0 Once control is established, a role call will be taken to ensure all concerned ( parties are on the line. NOTE: PEMA can no longer be contacted via the Gold Phone. PARS must be relayed via telephone at (717) 651-2001. Gold Phone Roll Call (Dial "* XX")
- 40 BCEMA yes/no
- 70
. OEMA yes/no
- 60 CCEMA yes/no
- 80 WVOES yes/no
- 50 HCOES yes/no O
( v' 3 23 Rev.9
EPP/ Implementing Procedures EPP/IP 4.1 AS.715FZ OFFSITE PROTECTIVE ACTIONS A'ITACIIMENT 5 (6 of 7) GOLD PHONE PROTOCOL l GOLD PHONE PAR CITECKLIST 2.1 Using the Bell line, contact PEMA (717-651-2001) and follow the instructions provided in Steps 4.0 and 5.0 of this Attachment. 3.0 When all appropriate States and Counties have responded to the Roll Call, provide information on Initial Notification Form, if appropriate. 4.0 When all appropriate States and Counties have responded to the roll call, the Emergency Director will relieve the DLC communicator. BVPS communicator: "Please remain on the line for Mr. (introduce the ED giving full name and title) who will provide the utility's Protective Action Recommendation." 5.0 The Emergency Director should introduce himself by name and title and then forward the utility's PAR and the reasons why this PAR was made. BVPS ED: "This is (name and title) . The f emergency classification is currently at the General Emergency and was declared at . The following is the Protective Action Recommendation by BVPS" (Provide the complete PAR and the basis for the recommendation. The ED will then answer any questions concerning the PAR.) l l l l 24 Rev.9
. . - _ _ - . . . _ . . _ - _ _ . _ _- ~ _ - _ _ _ _ . . . ... . _ . . _ . . . _ _ _ _ _ _ . _ _ . _ _ _ . ___ EPP/ Implementing Procedures EPP/IP 4.1 AS.715FZ p) s OFFSITE PROTECTIVE ACTIONS l I ATTACIIMENT 5 (7 of 7) GOLD PIIONE PROTOCOL GOLD PIIONE PAR CIIECKLIST 6.0 After the Protective Action Recommendation has been given and all parties completely updated, the DLC Emergency Director shall relinquish the line. At this time, the States and Counties are free to use the Gold Phone following the established protocol. l BVPS ED: "If there are no other questions, this concludes the utility's PAR. j Please inform the utility what protective actions are taken by your respective States. " Date/ Time: Signature: m ' .( f)~ v 25 Rev.9
EPP/IP 4.1 EPP/ Implementing Procedures OFFSITE PROTECTIVE ACTIONS
<O INTENTIONALLY BLANK i
(- l l l l l 26 Rev.9
-- - - - - - - - - - - _ - - - _ _ _ ' -- - - _ _ _ _ _ _ _ _ _ _ _ - - - - - - - ~ - ' - - - - - - - _ _ _ _ _ , _ _ _ , _ _ _ _
. _ . . _ _ . _ . . _ . _ . . _ . . _ _ . _ . . - . . . . . . . . . . _ - . ~ _ _ _ _ _ _ _ _ . . . . _ . . . _ _ _ _ . _ _ _ . . _ _ _ _ _ _ . _ _ _
BEAVER VALLEY JOB PERFORMANCE MEASURE ! EVALUATOR COVER SHEET O JPM Number: ADM-Emer Ex JPM
Title:
Determine Emergency Exposure Limit Rev:0 System #:2.3 K/A
Reference:
2.3.4 [3.1) Task ID #: 343 029 0302 JPM Application: Requal X Initial Exam Training Evaluation Method LOCATION TYPE i X Perf'rm C Plant Site - Training O Simulate Simulator D Annual Requal. Exam X Classroom E OJT X Initial Operator Exam - E Other:
. Administered By:
~
u BV-T E NRC , i Other: Evaluation Results Performer: Name: Employee No: Results E SAT Time-(minutes) E UNSAT* Allotted: 20 Actual: Time Critical: U Yes X No Administrative JPM X Faulted !
- Comments (Required for UNSAT Evaluation):
Evaluation Results E Check here if same as above Observer 1: Name: Employee No: Observer 2: Name Employee No: Observer 3: Name Employee No: Observer 4: Name Employee No: Time (minutes) Results Question ID Allotted Actual SAT UNSAT* Question #1 N/A u Employee No: - Question #1 N/A Q g Employee No:
- Comments (Required for UNSAT Evaluation):
, Evaluator ( P rint )' : Organization:
Evaluator Signature Date: After Val
RTL #AS.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE
,S CANDIDATE DIRECTION SHEET ! a 5- / THIS CHEET TO BE GIVEN TG CANDIDATE
- Read:
Task, the maximum allowable limits for emergency l Determine exposure. INITIAL An Alert has been declared at Unit 2 due to LOCA. An . perator has slipped an fallen in the VCT cubicle CONDITIONS
- while troubleshooting erratic VCT level indications.
e The operator is bleeding profusely, from the scalp. Health Physics has determined extremely high radiation exista in the VCT cubicle. The emergency squad believes the individual will bleed to death if he doesn' t receive prompt medical attention. The Unit 1 ANSS has volunteerad to enter the VCT cubicle to extract the victim. His Rad worker qualifications are current for BVPS and Rad con supervision has briefed him on the risks associated with his projected dose for the extraction of the operator from-the VCT ('")! ('~ cubicle. Jim Cross (Duquesne Light Chief Nuclear Officer) has been briefed of the situation and has NOT, and WILL NOT authorize additional exposures.. Determine the
' IYouaretheEmergencyDirector.
emergency exposure limitation for the Unit 1 ANSS to perform this extraction. At this time, ask the evaluator any questions you have on this JPM. When satisfied that you understand the assigned task, announce "I am now beginning the JPM". Simulate performance or perform as directed the required task. Point to any indicator or component you verify or check and announce ycur observations. . After determining the Task has been met, announce "I have completed the JPM". Then hand back this sheet to the evaluator.
. ,< g
(
~J After Val
-RIL HA5.635.J BEAVER VALLEY' JOB PERFORMANCE MEASURE j EVALUATOR DIRECTION SHEET
\
JPM MUMBER: ADM-Emer Ex
- JPM TITLE: Determine Emergency Exposure Limit TASK STAN: Determine the maximum allowable limits for emergency exposure.
RECOMMENDED. Control Room / Simulator STARTING LOCATION: DIRECTIONS: Determine maximum allowable limits for emergency exposure.
~
-INIT. CONDITIONS:
An Alert has been declared at Unit 2 due to LOCA. An operator has slipped an fallen in the VCT cubicle while troubleshooting erratic VCT level indications. The operator is bleeding profusely,-from the scalp. Health Physics has determined extremely high radiation exists in gs the VCT cubicle. The emergency squad believes ( : the individual will bleed to death if he
'-- - doesn' t receive prompt . medical attention. The Unit 1 ANSS has volunteered to enter the VCT cubicle to extract the victim. His Rad worker
. qualifications are current for BVPS and Rad con supervision has briefed him on'the, risks.
associated with his projected dose 'for the extraction of the operator.from the VCT
, cubicle. Jim Cross (Duquesne Light Chief Nuclear Officer) has been briefed of the situation and has NOT, and WILL NO'r authorize additional exposures.
-INIT. CUE: You are the Emergency Director. Determine the emergency exposure limitation for the Unit 1 ANSS to perform this extraction. _
REFERENCES:
EPP/IP 5.3, Rev. 7 TOOLS: None HANDOUT: After Val
.l ,
. RTL' #AS . 63'5. J
- - n -
NUMBER TITLE ADM-Emer Ex- Determine Emergency Exposure Limit i
' STEP STANDARD
.(Indicate "S" for Sat. or "U" !
("C" denotes critical step) for Unsat.) J i i START TIME: . i
- 1. Locate correct procedure. 1. Obtains EPP/IP 5.3.
I Comments: l
]
6 i I
- . NOTE
- Steps 2 through 8 follow 'j L-
}
flow-path of Att. 1. The ' kJ -~ information~can be obtained ' from other' locations in the procedure.
- 2. Verify.that there is a' 2 . Identifies that an Alert declared emergency. has'been declared.
Comments: j EVALUATOR CUE: An Alert was given in the initial conditions. . l I _\ o j l Page lof 4 After Val i- - I
7 RTL #AS.635.J-t i fN. .
.- NUMBER TITLE ADM-Emer EX Determine Emergency Exposure Limit !
~
STEP STANDARD (Indicate "S" for Sat. or "U"
.("C" denotes critical step) for Unsat.) 1
. .l
- 3. Verifies individual is 3.1 Verifies with Health qualified as radiation Physics that the individual worker, and are not declared are radiation workers.
. pregnant.
3.2 Verifies that ANSS is NOT declared pregnant. Comments: r
- (. EVALUATOR CUE: The necessary information was given in the initial conditions.
- 4. Identify that'the exposure 4. Verifies the exposure is is necessary to Save a human' necessary to Save'a human
-life. life.
Comments:
)
l l EVALUATOR CUE: Initial Conditinns - l indicated this need. t l-
./ ,
A 1 Page 2of 4 After Val
i RTL #AS.635.J Lo. : NUMBER TITLE l -.
'ADM-Emer EX Determine Emergency Exposure Limit STEP STANDARD L (Indicate _"S" for Sat. or "U" L
("C"' denotes critical step) for Unsat.) l S. Determine if the individual 5.1 Vcrifiea the individual is is a volunteer, a volunteer. E Comments: , l 1 l EVALUATOR CUE: This information I was given in the initial 1
. conditions. [
cL)
- EVALUATOR CUE
- If asked, provide -
cue that the ANSS h5s no previous ! ! emergency exposures. L
- 6. Determine if the Unit 1.ANSS _6 . Verify that the Unit 1 ANSS has been briefed, has been briefed.
Comments: I EVALUATOR CUE: This information was given in the initial conditions. l L O i-l3 l Page 3of 4 After Val 1 .. t ' ,. -. , ., _
RTL #A5.635.J
~
.O NUMBER TITLE ADM-Emer.EX Determine Emergency Exposure Limit STEP STANDARD (Indicate "S" for' Sat. or "U"
.("C" denotes critical step). for Unsat.)
- 7. Determines that the DLC 7.. Verifies that the DLC chief chief Nuclear officer has Nuclear officer has no't :
not authorized exposures authorized exposures > 75 l
>75. Rem. Rem.
EVALUATOR CUE: This information was given in the initial conditions. ; ,/ 8.C Determine the allowable 8.C Determines that the 'V dose. allowable dose will be 75 l- Rem TEDE,-225 Rem lens of eye and 750 Retn organ CDE. Comments: STOP TIME l~ l-r
- i. 1 l
t i ! ! I l i f'g . r 'd . 3 Page 4of 4 After Val J s-w w . , , - - , . - - . . - - - . ,. , m- ,
(O EPP/IP 5.3 A1.002L l
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3 4 - 1 i i-L
,q . EMERGENCY EXPOSURE CRITERIA AND L('V CONTROL i
usg0M 1 YOR W' O A- Rev. 7
. ,~y Al EPP/ Implementing Procedure EPP/IP 5.3 A1.002L EMERGENCY EXPOSURE CRITERIA AND CONTROL APPROVAL PAGE Intent Related Revision Yes X No IF YES OSC and Site Approval OSC Meeting Number Date NOTE: The approval of this revision by the Onsite Safety Committee ensures the f~v requirements of 10 CFR 50.54(q) have been considered and not compromised.
,i T
,v)
Reviewed !- Director, Emergency Preparedness Date l
' Approved Manager-Nuclear Safety Date l
l~ IF NO - Reviewed b > Sw R 2" 1'l Director,' Emergency Prepared' ness / D' ate Approved & // 22-b
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N.x - Manager-Nuclear Safet) Date
@@Q@g@ Rev.7
. namwwwm
t .. . EPP/ Implementing Procedure EPP/IP 5.3 l' EMERGENCY EXPOSURE CRITERIA AND CONTROL EFFECTIVE INDEX Issue 8 Rev. 0 OSC Approved 3-12-87 Issue 9 Rev, 0, Non-Intent Related 10-9-90 1 Non-Intent Revision 11-21-91 2 Non-Intent Revision 12-29-92 Rev. 5 OSC Approved 12-2-93 6 Non-Intent Revision 11-15-94 O l7 Non-Intent Revision 12-1-95 y l0 i 11 Rev.7
4 t 4 g, EPP/ Implementing Procedure EPP/IP 5.3 i
- EMERGENCY EXPOSURE CRITERIA' AND CONTROL h-s
! ~ TABLE OF CONTENTS
!' 4 A. Purpose B. References A
! <ly C. Responsibilities D. Action Levels / Precautions
- E. Piocedure 1
F. Final Condition f ,.. . of Attachments o iii Rev.7-
.v
.,,;.,,+-
y 1 3 EPP/ Implementing Procedure . EPP/IP 5.3
~
EMERGENCY EXPOSURE CRITERIA AND CONTROL A. PURPOSE ! This procedure provides guidance and criteria for dose limitation in situations where it may be necessary for individuals to exceed established exposure limits to save a life or e to minimize the consequences of an accident. Authorization for such exposures is provided by 10 CFR 50.47(B)(11).
-IL ' R EFERENCES 1.0 Beaver Valley Power Station Emergency Preparedness Plan and Implementing Procedures.-
2.0 ICRP- Publication 26, " Recommendation of the International' Commission on Radiological Protection"
.p 3.0 ICRP Publication 28, "The Principals and General Procedures for Handling
.( Emergency and Accidental Exposures of Workers"
~4.0 EPP 400-R-92/01 (and subsequent revisions), " Manual of Protective Action Guides and Protective Actions for Nuclear Incidents" 5.0 Title 10, Code of Federal Regulations Part 20 l
6.0 - Title 10, Code of Federal Regulations Part 50 7,0 #EG-0654/ FEMA-REP-1 " Criteria for Preparation and Evaluation of
. alogical Emergency Response Plans and Preparedness in Support of Nuclear Power Plants."
' 8.0 BVPS Health Physics Manual I 9.0 NUMARC, . Implementation of the New EPA Protective Action Guides in Existing Emergency Programs D
.d l
1- Rev.7 i
EPP/ Implementing Procedure EPP/IP 5.3 EMERGENCY EXPOSURE CRITERIA AND CONTROL C. RESPONSIIIILITIES The Emergency Director has the responsibility and authority to ensure that the radiation exposure of personnel performing functions necessary to contend with the emergency condition, are maintained As Low As Reasonably Achievable (ALARA) and in keeping with the provisions of this EPP/IP. The Emergency Director is the only individual who may authorize dose extensions in excess of 10 CFR 20. D. ACTION LEVELS / PRECAUTIONS / CRITERIA 1.0 ACTION LEVELS 1.1 An emergency condition at the Beaver . Valley Power Station has resulted in radiation levels within the Station greatly in excess of normal levels which require special considerations for exposure control. 2.0 PRECAUTIONS 2.1 Emergency exposure limits apply only to Duquesne Light and contractor personnel who are qualified as radiation worke..' at the Beaver Valley Power Station and have been issued BVPS dosimetry. 2.2 The establishment of these emergency exposure controls in no manner suggests that the exposures are acceptable. Although 10 CFR 50.47(b)(ll) requires that the EPP contain emergency exposure control measures, any exposure greater than 10 CFR 20 provisions is reportable to the NRC. 3.0 CRITERIA _ 3.1 Definitions 3.1.1 Accident Exposure: Exposure to radiation or radioactive materials that results from an unexpected event. Accident exposure refers to the immediate consequences of the unexpected event and the immediate corrective / mitigative actions of personnel present at the scene when the event occurred. Accident exposures are not controlled by the Health Physics Manual (HPM) or the Emergency Preparedness Plan (EPP), but may be reportable to the NRC under 10 CFR 20 and/or 10 CFR 50.72. 2 Rev. 7
i h EPP/ Implementing Procedure EPP/IP 5.3 EMERGENCY EXPOSURE CRITERIA AND CONTROL l 3.1.2 Emereency Exposure: Exposure to radiation or radioactive materials that is the result of actions taken in response to an l emergency condition classified and declared pursuant to the BVPS Emergency Preparedness Plan. Emergency exposure refers to radiation exposure caused by those assessment, l' corrective, and mitigative actions that are required on an l immediate basis to save human lives, or to prevent or minimize the collective exposure of large populations. Such activities are directed by the Control Room or by the TSC/ EOF. Planned Special Exposures (see 3.1.4) are not considered emergency exposures. 3.1.3 Life Savine Action: Those actions related to the search and rescue of injured persons. ( 3.1.4 Planned Special Exposure (PSE): As defined in 10 CFR 20, an I~. infrequent exposure to radiation, separate from and in addition to the annual dose limits. The HPM delineates requirements to be 4 met in classifying an exposure as a PSE. PSEs might be warranted in the recovery phase. However, it is unlikely that the PSE requirements could be met during the initial phases of the r. emergency. 3.2 All emergency exposure extensions are subject to the following conditions: 3.2.1 All exposures shall be maintained such that the TEDE is as low as reasonably achievable during emergencies, noting that it may ~ be necessary to tradeoff individual personal exposure against collective population exposure offsite, or in the interest of saving human lives. i 3.2.2 Emergency exposure limits apply only during emergencies declared pursuant to the Emergency Preparedness Plan. 3.2.3 The Emergency Director, with the advice of the Radiological
.fi Controls Coordinator, shall approve all emergency exposures in V excess of 10 CFR 20 limits. This approval shall be documented, j -- However, the approval may be relayed verbally and documented later.
l 3 Rev.7
EPP/IP 5.3 EPP/ Implementing Procedure EMEltGENCY EXPOSUltE CIllTEltlA AND CONTitOL 3.2.4 Emergency Exposure limits apply only to Duquesne Light and contractor personnel who are qualified as radiation workers at the Beaver Valley Power Station and have been issued BVPS dosimeters. 3.2.5 Personnel who have received previous accident or emergency . exposure in excess of 25 rem TEDE shall not participate in further emergency exposure situations. 3.2.5.1 Since accident and emergency exposures are not required to be included in personnel exposure histories, it may lie necessary to interview contractor and visitor personnel regarding such exposures. 3.2.6 Personnel who have declared pregnancy in accordance with the HPM, shall not participate in emergency exposure situations. . 3.2.7 With the exception of emergency exposures in excess of 25 rem TEDE, participation in emergency exposure situations need not be voluntary on the part of the individual emergency worker. 3.2.8 The dose of personnel authorized to receive emergency exposures shall be monitored and recorded as provided in the Health Physics Manual. 3.3 Exposure Limitation 3.3.1 Except as provided below, control of radiation exposures during , an emergency shall be governed by the HPM. 3.3.2 The exposure of emergency response organization personnel should be maintained such that routine radiation exposure limits and administrative controls contained within the HPM are met. These routine exposure limits may be exceeded during the performance of emergency activities identified in paragraphs 3.3.3 - 3.3.5, provided that the conditions of paragraph 3.2 are met. 4 Itev. 7
) EPP/ Implementing Procedure EPP/IP 5.3 EMEltGENCY EXPOSURE CRITEltIA AND CONTitOL 3.3.3 For activities performed on an immediate basis to prevent the failure of equipment necessary to protect the public health and safety, the TEDE of personnel directly involved shall not exceed 10 rem. This limit is applicable only if actions establishing adequate or equivalent protection, with a lower dose consequence, are not readily available.
3.3.4 For activities necessary on an immediate basis (1) to save human life, (2) to restore equipment necessary to maintain critical safety functions or to establish and maintain a safe shutdown, or (3) to prever.t or mitigate a release of radioactivity to the environment l for which offsite protective measures may be required, the TEDE of personnel directly involved shall not exceed 25 rem. This limit is applicable only if actions establishing adequate or equivalent protection, with less dose, are not readily available. 3.3.5 For activities necessary on an immediate basis (1) to save human life, (2) to restore equipment necessary to maintain critical safety functions or to establish and maintain a safe shutdown, or (3) to prevent or mitigate a release of radioactivity to the environment for which offsite protective measures may be required, the TEDE
, of personnel directly involved may exceed 25 rem, provided:
3.3.5.1 This limit is applicable only if actions establishing adequate or equivalent protection, with less dose, are not readily available, and, 3.3.5.2 Personnel assigned to these activities shall be - volunteers, and, 3.3.5.3 Personnel assigned to these activities shall be briefed on, and understand, the risks associated with the estimated radiation exposure. For life L saving activities, this briefing shall include a discussion on the probability of a successful O rescue, and, ,V l 5 Rev.7 i
EPP/IP 5.3 EPP/ Implementing Procedure EMERGENCY EXPOSURE CRITERIA AND CONTROL 3.3.5.4 Concurrence of the Company Chief Nuclear Officer, or designee, shall be obtained for any exposure projected to exceed 75 rem TEDE. 3.3.6 In addition to the TEDE limits established above, the dose equivalent to the lens of the eye shall be limited to three (3x) the limits specified in paragraph 3.3.3 and 3.3.4 above. The CDE to any organ (including the skin and body extremities) shall be limited to ten (10x) the limits specified in paragraph 3.3.3 and 3.3.4 above. 3.4 The internal exposure of BVPS emergency workers performing activities in the environment (i.e., outside plant buildings) is monitored and controlled as follows: 3.4.1 Monitoring of intemal exposure and assessment of CEDE may be waived for BVPS field monitoring team members under the ( following conditions: 3.4.1.1 The emergency involves a substantial core melt sequences with actual or potential early containment failure or bypass, and, 3.4.1.2 The release plume is present in the areas where the personnel are assigned, and, 3.4.1.3 An evacuation of the public has been ordered, but is incomplete, and, _ 3.4.1.4 The field monitoring team is assigned tasks out-of-doors associated with quantifying an unmonitored release from the plant in support of decisions related to the need for extending protective measures, and, O 6 Rev.7
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y,I EPP/ Implementing Procedure EPP/IP 5.3 EMERGENCY EXPOSURE CRITERIA AND CONTROL 3.4.1.5 If the DDE is likely to exceed 5 rem (i.e., assumes DDE to TEDE ratio of 5) for the duration of the exposure, personnel involved shall be volunteers, and, shall have been briefed on, and understand, the risks associated with the estimated radiation exposure and .the . uncertainty regarding the unmonitored CEDE, and, 3.4.1.6 If the DDE is likely to exceed 5 rern (i.e., assumes DDE to TEDE ratio of 5) potassium iodide shall be issued, and, 3.4.1.7 Conditions for emergency exposure delineated in paragraph 3.2 Opply to these individuals. g 3.4.2 Monitor'ng of internal exposure and assessment of CEDE of (d emergency personnel working out-of-doors shall be accomplished by establishing pocket dosimeter administrative guides set at that value of DDE that would maintain the sum of the DDE and CEDE below limits specified in paragraph 3.3. In addition: 3.4.2.1 These adjustments should be made using EDE to TEDE ratios determined from dose projections performed during the emergency using actual release source terms, if available. Ratios determined prior to the release from default source terms may be useful as bounding values. 3.4.2.2 These dosimeter administrative guides shall be adjusted on the basis of actual field monitoring data, as these data become available, and, 3.4.2.3 Conditions for emergency exposure delineated in paragraph 3.2 apply to these individuals. n ;' ( NJ 7 Rev.7
EPP/IP 5.3 EPP/ Implementing Procedure EMERGENCY EXPOSURE CRITERIA AND CONTROL 1 3.4.3 Monitoring of internal exposure and assessment of CEDE is not , l required if the release has not started, or if plume is no longer I present, as this reduces the potential for uptake such that CEDE is negligible. In this case, emergency worker administrative guides are based on DDE. 3.5 Post-Exposure Evaluations 3.5.1 Personnel receiving emergency or accident exposures should be restricted from further occupational exposure pending the outcome of exposure evaluations ar.d, if necessary, medical surveillance. 3.5.2 An exposure evaluation shall be performed to determine the individual dose. This dose may include assessment of the following dose quantities as applicable to the exposure situation: SDE, DE, DDE, ALI, CDE, CEDE, and TEDE. This ( evaluation should be based on observed area dose rates, airborne activity measurements, and dosimetry results. This evaluation shall be documented in an appropriate format and filed with the individual's exposure records. Appropriate reports shall be submitted to the Onsite Safety Committee and the USNRC. 3.5.3 If an individual's external dose exceeds 10 rem DDE, 30 rem dose equivalent to the lens of eye, and/or 100 rem dose equivalent skin or an extremity, the details of the exposure incident shall be brought to the attention of a physician. The physician shall determine the need, extent, and nature of any , clinical, biological, or biochemical examinations. 3.5.4 If an individual's external dose exceeds 25 rem DDE,150 rem dose equivalent to the lens of eye, and/or 250 rem dose equivalent skin or an extremity, the individual shall be examined by a physician. - The physician shall determine the need, extent, and nature of any clinical, biological, or biochemical examinations, or necessary medical surveillance. 8 Rev.7
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' EPP/ Implementing Procedure EPP/IP 5.3 i
EMERGENCY EXPOSURE CRITERIA AND CONTROL 3.5.5 If an individual's intake exceeds 1.0 ALI, the details of the exposure incident shall be brought to the attention of a physician. The physician shall determine the need, extent, and nature of any clinical, biological, biochemical examinations, or necessary medical treatment. E. PROCEDURE L 1.0 In the event emergency exposure is necessary, the following actions should be performed. Although it is preferable to perform and document these steps prior to the exposure, if necessary the Emergency Director may verbally authorize the inercased exposure and complete the documentation at a later time. 1.1 Per Attachment 1, determine the appropriate Emergency Exposure Authorization Limit. [. E l
. 1.2 Complete Section A of the Emergency Exposure Authorization Form (Attachment 2). Line 6 of the form must be signed by the Emergency Director. !
1.3 The individual to receive the_ increased exposure will complete Section B. 1.4 The individual will be briefed on the radiological and other conditions in the area (or expected in the area), the tasks to be performed, ALARA measures applicable to the task, and contingency measures, prior to entry to the affected area. Included in this briefing shall be a discussion of the biological risks associated with the exposure to be incurred. - 1.5 The individual performs the assigned tasks. ! 1.6 Following the exposure, the Radiological Controls Coordinator, or y designee, will complete and sign Section C and D of the Emergency l Exposure Authorization Form. p 9 Rev.7 L.
EPP/IP 5.3 EPPilmplementing Procedure EMEltGENCY EXPOSURE CRITEltlA AND CONTROL F. FINAL CONDITIONS This procedure will be terminated when all sections of Attachment 1, " Emergency Exposure Authorization Form" have been completed and/or assignments are made for necessary exposure reports. The original of Attachment I should be filed in the , individual's personnel exposure history records and a copy sent to the Manager, EPP for inclusion in event records. G. ATTACIIMENTS 1.0 Emergency Exposure Authorization Limits 2.0 Emergency Exposure Authorization Form
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( ' d ( l l 10 Rev.7
1 { CHANGES TO INDIVIDUAL WALK-THROUGH TEST OUTLINE NOTE: All changes to the original outline are in BOLD /TAL/CS on the revision 1
' outline.
I 1.. Question # a of JPM 2 had a typographical error. The word Reactivity. should have been Density. A 2. Question # b of JPM 3 changed planned follow up question from a refueling cavity flowpath to a transfer to recirculation flowpath questibn. Unit 2 does not use the ECCS flowpath to drain the refueling cavity, rather they use ' ! RHS and fuel. pool cooling. 4 1 4-
- O
l ,] ES-301 Individual Walk-Through Test Outline Form ES-301-2 'w) , 1 Facility: _ Beaver Vallev Power Station Unit 2_, Date of Examination: 8/17/98 Exam Level (circle one): RO / SRO(l) / SRO(U) Operating Test No.: _2 LOT 2A_ l l System /-JPM Title / Type Safety Planned Follow-up Questions: Codes
- Function K/A/G - Importance - Description
- 1. CVCS / Perform manual I a. 004 A3.09 (3.2) Response to failed make-up to charging pump VCT level suction (2CR-581)
D-A-S b. 004 A2.32 (3.9) Reactivity change-new mixed bed
- 2. PZR Level Control System - 11 a. 011 K4.03 (2.9) Density !
Respond compensation /PZR level to a failed level channel l transmitter N-S b. 028 AK1.01 (3.1) PZR reference leg leak
- 3. ECCS - Transfer to Cold Leg Ill a. 2.1.12 (4.0) Accum. TS level below !
Recirc LCO , I (2CR-529) m D-A-S b 006 K1.03 (4.3) Transfer to Hotley
) Recirculation Flowpath \# 4. RHS - Respond to Loss of IV a. 005 A2.02 (3.7) Cold OPPS operation RHS (2CR-094)
D-S-L b. 005 A4.01 (3.4) Purpose /use of ' Test' pushbutton
- 5. AC Elect. - Transfer Bus 2AE VI a. 055 EA1.06 (4.5) D/G trip blocks on from Bus u/v Emergency to Normal (2CR-097)
D-S b. 062 A3.05 (3.6) NSA for Vital Bus Power ( ')
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NUREG-1021 BVPS 2 LOT 2A Revision 1 1 of 2 Interim Rev. 8, January 1997
-_ ._ _ . _ . . - . . -.m. _ . _ _ . _ . _ _ . . . _ . _ . _ .
1 l
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-(") 6. Process Rad Monitor -
Respond to a Vil a 076 AK3.06 (3.8) Actions required E Tech Spec Rad Monitor Alarm (2CR-622) D-A-S b. 2.2.25 (3.7) Bases for Specific Activity q
- 7. WGDS - Discharge Gas Decay IX a. 071 A4.07 (3.0) Confirm Bleed Rate Tank.
N-S. b. 071 A2.08 (2.8) Stability Class explanation
- 8. AFW -Isolate AFW during IV a. 061 K4.04 (3.4) Prevertion of AFW I Alternate runout Safe Shutdown N-P-R b. 2.2.25 (3.7) T.S. Bases for PDWST 9.' DC Elect. - Charge battery 2- VI a. 063 K1.04 (2.7) Battery ventilation 1 3 using OOS, Required actions for battery room Spare Battery Charger (2PL-050) entry
- b. 063 K4.02 (3.2) Purpose of RCPBP panels
- 10. HRPS - Locally start V a. 028 K5.01 (3.9) Sources of Hydrogen j Hydrogen Analyzers (2PL-047) in containment D-P b. 2.1.12 (4.0) T.S actions if both lp- Hydrogen Analyzers are OOS
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- Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room, (S)imulator, (L)ow-Power, (P)lant, (R)CA i
'T 1
l ( NUREG-1021 2 of 2 Interim Rev. 8, January 1997
-BVPS 2 LOT 2A Revision 1
a t i j RTL #AS.6400 BEAVER VALLEY JOB PERFORMANCE MEASURE l EVALUATOR COVER SHEET JPM Number: 2CR-581 Rev: After Val System #: 004 } JPM
Title:
Perform Manual Makeup to Charging Suction l { K/A
Reference:
004020A4.01 3.8/3.3 Task ID 4: 0040250101 l 004A4.07 3.4/3.7 Rev.1 l JPM Application: x Requal E Initial Exam Training Evaluation Method LOCATION TYPE 1 i f Perform Plant Site . Training l i Simulate Simulator O Annual Requal. Exam , l Classroom OJT l Initial Operator Exam l { Administered By: Other: BV-T
- NRC Other
l l l Evaluation Results Performer: Name: Employee No: i Results SAT Time (minutes) UNSAT* Allotted: 15 Actual: i Time Critical: Yes X No Administrative JPM Faulted X
- Comment (Required for UNSAT Evaluation):
Evaluation Results Check here if same as above Observer 1: Name: Employee No: Observer 2: Name Employee No: Observer 3: Name Employee No: Observer 4: Name Employee No: Time (minutes) Results Question ID Allotted Actual SAT UNSAT* Question #1 O Employee No: Question #2 O Employee No:
- Comments (Required for UNSAT Evaluation):
Evaluator (Print): Organization: Evaluator Signature Date: After Val
RTL.'#AS.635.J. BEAVER VALLEY JOB PERFORMANCE MEASURE CANDIDATE DIRECTION SHEET I -O
- THIS SHEET TO BE GIVEN TO CANDIDATE
- Read: !
Task: Perform Manual Makeup to Charging Suction INITIAL CONDITIONS: The. plant is in Mode 1. RCS b.oron ; concentration is 720 ppm. Boric acid tank concentration is 7200 ppm. The . , automatic control circuitry of the Reactor Makeup Control System-is maintaining VCT level at 22%. Reactor Makeup control is in AUTOMATIC, but an investigation into the Reactor Makeup , Control System is in. progress. I&C requests that VCT. level be raised to 42% as part of their troubleshooting efforts. All procedural Initial Conditions are satisfied. j
.m
.s INIT. CUE: Your supervisor directs you to increase VCT level to 42% at 75 gpm by performing a Manual Makeup to the VCT.
At this time, ask the evaluator any questions you have on this ; JPM. When satisfied that you understand the assigned task, announce "I am-now beginning the JPM". Simulate performance or perform as directed the~ required task. Point'to any indicator.or component you verify or check and announce your observations. After determining the Task has been met, announce "I have completed the JPM". Then hand back this sheet to the , evaluator. l I
.[ \r After Val
i RIL #AS.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE [~ ' EVALUATOR DIRECTION SHEET (,s JPM NUMBER: 2CR-581 JPMLTITLE: Perform Manual Makeup to Charging Suction TASK STAN.: . . VCT level is increased to approximately 42% and makeup flow is stopped. RECOMMENDED STARTING LOCATION: CONTROL ROOM , i DIRECTIONS: You are to simulate (perform) the task Perform Manual Makeup.to Charging Suction. . t INIT. CONDITIONS: The plant is in Mode 1. RCS boron concentration is 720 ppm. Boric acid tank ; concentration is 7200 ppm. The automatic control circuitry of the Reactor Makeup s Control System is maintaining VCT level at 7 I 22%. Reactor Makeup Control is in
%I AUTOMATIC, but an investigation into the Reactor Makeup. Control System is in progress. I&C requests that VCT level be raised to 42% as part of their troubleshooting efforts. All procedural Initial Conditions are satisfied.
.Your supervisor directs you to increase'VCT
- level to 42% at 75 gpm by performing a Manual Makeup to the VCT. ]
l
REFERENCES:
20M-7.4.N Issue 4 Revision 3 L . TOOLS : None HANDOUT: 20M-7.4.N !g. 4 t 1 9 i-After Val
I 4 , RTL #AS.635.J ,
* -
- THIS SHEET TO BE GIVEN TO CANDIDATE *
- BVPS-JOB PERFORMANCE MEASURE
-ORAL QUESTION #1 The plant is operating at 100% power, all systems in NSA. VCT level transmitter 2CHS*LT115 fails to 100% level indication.
With-no operator action, briefly explain-the effect this will-have on VCT level control. +. l i , i
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h 1: I O <. t G - After Val
.m... ..
+ .
RTL #A5.635.J BVPS JOB PERFORMANCE MEASURE O. ORAL QUESTION #1 The plant is operating at 100% power, all systems in NSA. VCT level transmitter 2CHS*LT115 fails to 100% level indication. With no operator action, briefly explain the effect this will have on VCT level control. ANSWER: .VCT level control valves 2CHS*LCV1'12 and 2CHS*LCV115 will both go to full divert to ' BRS. . Actual VCT level will'begin dropping. With no operator action, the VCT will empty since AUTO makeup is controlled by ' 2CHS*LT115. AUTO swapping of the charging pump suction to the RWST will not occur since the logic is 2/2 < 5% level. TIME 3 minutes ALLOTTED: KSA #: 004A3.09 3.3/3.2 Rev. 1 yN 004010A3.05 3.3/3.2 ms s REF: 20M-7.5 figure 7-51 VCT Level Control issue 4 rev. O page 1 COMMENTS:
.; V After Val
RTL #AS.635.J ym
.g i
*
- THIS SHEET TO BE GIVEN TO CANDIDATE *
- BVPS JOB PERFORMANCE MEASURE ORAL QUESTION #2
-The plant is operating at 100% power, all systems in NSA.
Chemistry contacts you and requests Mixed bed demineralizer(2CHS*DEMIN21B1 be placed into service, and Mixed bed demineralizer[2CHS*DEMIN21A) be removed from service. Mixed , bed demineralizer[2CHS*DEMIN21B] has been charged with new resin. What are the' potential reactivity affects ass 6ciated with this evolution? How are they minimized? O After Val
RTL'#A5.635.J BVPS JOB PERFORMANCE MEASURE f,-sg ORAL QUESTION #2
- . The' plant is operating at 100% power, all systems in NSA.
Chemistry contacts you and requests Mixed bed demineralizer[2CHS*DEMIN21B) be placed into service, and Mixed bed demineralizer[2CHS*DEMIN21A] be removed from service. Mixed l bed demineralizer[2CHS*DEMIN21B) has been charged with new I resin. What are the potential reactivity affects associated with this evolution? How are they minimized?
~
ANSWER: An insertion of positive reactivity is possible due to absorption of boron in the bed. Minimized b'y b'oron saturating the new resin PRIOR to opening the outlet effluent valve. [ Purging the bed through the sample line). TIME 2 minutes ALLOTTED: KSA #: 004A2.32 3.4/3.9 Rev.1 004020A2.13 3.4/3.9 O)
\~- .REF: 20M-7.4.AM.II P&L B, issue 4 rev. 4 20M-7.4.AM.IV.A.4 p 2 of 15 issue 4 rev. 4 COMMENTS:
L' After Val
RTL'#A5.635.J NUMBER TITLE 2CR-581 Perform Manual Makeup to Charging Suction STEP STANDARD (Indicate "S" for Sat. or "U"
.("C" denotes critical step) for Unsat.) .
Start time: EVALUATOR NOTE: Only provide cues if simulating performance of this task. Simulator Setup IC-18. Verify.VCT level B at 22%. CLF VLV BAT 10, 1, 0, D. To fail 2CHS-FCV113A () Reset totalizer Closed. thumbwheels to zero
- 1. Obtain a copy of 20M- 1. Candidate locates 7.4.N " Blender Manual procedure.
Makeup Operations".
. COMMENTS:
- 2. Obtain the RCS boron 2. Candidate obtains the concentration, latest RCS boron concentration.
COMMENTS: I EVALUATOR CUE: The current RCS boron concentration is 720 ppm. Page 1 of 9 After Val. 1: L L .. . . . . . . . . . . . . . . . . . . . .
l RTL #A5'.635.J l ' je s I NUMBER TITLE 2CR-581 Perform Manual Makeup to Charging Suction l l STEP STANDARD I (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.) i l
'l EVALUATOR NOTE: Candidate !
may perform calculations for B.A. flow setpoint and 1 required volumes. prior to 'l board manipulation. j l
- 3. Place the " Boric Acid 3. Candidate: j Makeup Blender Control" '
to STOP position. (BB- 3.1 Locates control switch' ) A) and places switch in
- ("j the-STOP position.
N ,/ l 3.2 Verifies makeup control green light energizes. l EVALUATOR CUE: Switch in STOP position. Makeup. control' green light energizes. COMMENTS: l I i r I-
.r~
t 1 I Page 2 of 9 After Val. r
RTL #A5.635.J ('s i V) NUMBER TITLE 2CR-581 Perform Manual Makeup to Charging Suction STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.) 4.C P.1. aces " Mode Selector" 4.C Candidate locates switch to MANUAL. switch and places switch into MANUAL. COMMENTS: EyALUATOR CUE: Switch in
/'"N,; ~
&anual.
wJ
- 5. Set Total Makeup from 5. Candidate locates Blender Flow Totalizer Total Makeup from (for 320 gallons). Blender Flow Totalizer and adjusts counter
[to 320 gallons]. COMMENTS:
,r\ .
l Page 3 of 9 After Val.
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. . . _ . - .- _ _ _ _ - . . _ - - _ _ ~
RTL #AS.635.J (~)
'\ss/ NUMBER TITLE 2CR-581 Perform Manual Makeup to Charging Suction l STEP. STANDARD (Indicate "S" for Sat. or "U"
("C" denotes critical step) for Unsat.) 6.C Ad.just " Boric Acid to 6. Candidate: ; Boric Acid Blender" [2CHS*FCV113A) for 6.1.C Calculates boric acid desired concentration. flow (720 ppm x 75 gpm - (BB-A) ~/ 7200 ppm) = 7.5 gpm. 6.2 Dial pot turns (7.5 gpm/4) i 6.3.C Locates flow , controller and adjusts < l controller to approx. ] 188 units. ( 2 units). ) l l 1 E COMMENTS: I l 7. C. Adjust [2CHS* HIC 168), 7.1.C Candidate calculates L Blender Total Flow Auto Pot Set. = 75/16 = 4. 68 Setpoint, to the or 468 Units blender total flow of 75 gpm. i' L COMMENTS: l I 1 ,(
.Page 4 of 9 After Val.
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RTL #AS.635.J -r r NUMBER TITLE 2CR-581 Perform Manual Makeup to. Charging Suction l 1 STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.)- . l 8.C Adjust " Primary Grade 8.C Candidate-locates l
-Water to Boric Acid controller and adjusts i Blender" [2CHS*FCV114A) controller to ;
to the same value as approximately.75 gpm, [2CHS* HIC 168) of 75 468 units ( 2 units). ;
-9Pm.
i COMMENTS: ( ( . 1
- 9. Set Boric Acid Flow to 9. Candidate sets the l Blender Flow Totalizer Boric Acid Flow to for the total volume of Blender F. low Totalizer boric acid'to be added, at his/her discretion.
- 7.5 x = 320 - = 32 75 COMMENTS:
l i l l'3 k_s !
- l Page 5 of 9 After Val.
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._, , i
m . . ., . . _ . . _ _ _ _ _ . _ . . _ - . . _ . . . _ _ . . _ _ . _ . . . - _ . . . _ _ i l . - RTL #AS.635.J ] l
\ NUMBER- TITLE 2CR-581 Perform Manual Makeup to Charging suction
-l l
STEP STAlOARD (Indicate "S" for Sat. or "U" ("C"-denotes critical step) for ^;nsat.) 10 . . Verify the inservice 10. Candidate verifies
. Boric Acid Transfer inservice BATP is Pump is in AUTO. (BB-A) selected for AUTO operation.
COMMENTS:
. r's l 11.C Open Boric i Acid Blender 11. Candidate: ;
' (' 'Disch to Charging Punps
[2CHS*FCV113B). (BB-A) 11.1 Locates control switch for'2CHS*FCV113B. 11.2.C Place control switch to OPEN.
- 11.2 Verifies valve red light energized.
EVALUATOR CUE: 2CHS*FCV113B red light energized. COMMENTS: n.
' x_)
Page 5 of 9 After Val.
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RTL #AS.635.J lt"'Y t f
\/- NUMBER. TITLE.
2CR-581 Perform Manual Makeup to Charging Suction ! STEP ' STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.)
-12.C Places " Boric Acid 12.C Carididate places Makeup Control Switch" " Boric Acid Makeup to START. (BB-A) Control Switch" to l START.
EVALUATOR CUE: Switch in START. position. Makeup control red light energized. Inservice BA pump red light. energized. _ ,] Qf COMMENTS: 1 EVALUATOR NOTE: This is a L FAULTED JPM. No boric acid flow will occur during subsequent stept; I 1. l- ~ l 1 l Page 7 of 9 After Val.
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e RTL #AS.635.J
-(sus}/
r NUMBER TITLE 2CR-581 Perform Manual Makeup to Charging Suction STEP STANDARD _ (Indicate "S".for Sat. or "U" ("C" denotes critical step) for Unsat.) .
- 13 . Verify proper system 13. Candidate verifies: ,
response.
- 13.1 Boric Acid Transfer Pump in Auto AND ;
running. (BB-A) 13.2 Proper Boric Acid Flow l on recorder [2CHS-FR-113]. ] f N- : 13.3 Proper Total M/U Flow-From Blender on I
' recorder [2CHS-FR113]'.
(VB-A) EVALUATOR CUE: 2CHS*FCV113A green light energized (valve closed). ! 2CHS*FCV114A red and green lights energized-(valve throttled). Selected Boric Acid Transfer Pump red light energizes. After several seconds or when-asked, inform candidate Boric Acid flow is approx. O gpm and Total flow is p approximately 75 gpm. . !~ , COMMENTS: p ~. _ - i ,\ ..' Page 8 of 9 After Val.
\
l [ 'RTL #A5.'635.J I/~' r
)
NUMBER- TITLE ) i 2CR-581 Perform Manual Makeup to Charging suction STEP. STANDARD (Indicate "S" for Sat. or "U" i '. ("C" denotes-critical step) for Unsat.) . 3-i 14.C Can6' ate recognizes 14. Candidate: I ae dilution in
- progress and places 14.1 Recognizes that boric Boric Acid Makeup acid flow is,zero gpm.
- Control Switch to STOP.
14.2.C Candidate manually , stops makeup prior to
. reaching 42% VCT level. -
~ ("%
(,) EVALUATOR CUE: energizes, Green light i COMMENTS: EVALUATOR CUE: I&C will investigate the problem with 2CHS*FCV113A. It is not necessary to set up for Auto Makeup. (Use cue if candidate requests guidance.) EVALUATOR NOTE: Evaluator should terminate JPM at this point. Stop Time: i
'N J Page 9 of 9 After Val.
Record Type #A9.330B DUQUESNE LIGHT COMPANY Beaver Valley Power Station Unit 2 ., FOR TRAINiiVG USE ONLY 2OM-7.4.N BLENDER MANUAL MAKEUP OPERATIONS Issue 4 Revision 3 Prepared by Date Pagesissued Effective Date M. P. Flynn 01/02/98 N1 thru N6 JAN 161998 Reviewed by Date Validated by Date J. P. KeeDan 01/06/98 N/A OSC Meeting No. Date Approved by Date Non-Intent 01/08/98 jggg p, ,g
/
i mamma
@W@EH2
1 a Bsevar Valley Pow r Stttion Unit 2 2OM-7.4.N Chnmical and Volumn Control System Issue 4 Revision 3 Operating Procedures Page N 1 of 6 ( BLENDER M ANUAL MAKEUP OPERATIONS V
- l. PURPOSE A. This procedure provides the instructions for manual makeup to the reactor coolant system. This procedure may be entered into from an EOP.
II.- PRECAUTIONS & LIMITATIONS ! A. The effects of boration and dilution while the reactor is suberitical must be monitored by observing the source range count rate. If the ccant rate increases at an unexpected rate, the operation must be stopped.
- 3. The effects of boration and dilution must be monitored by observing the resulting changes in coolant average temperature (Tavg) and control bank movement. The ,
operation must be stopped if the control bank movement is in the wrong direction. ) C. Blend 9r manual makeup is permitted in Mode 4,5, or 6, but should be avoided if possible. Reference T.S. 3.t.2.9, " Isolation of Unborated Water Sources - Shutdown." D. All routine boration or dilution volumes, and rate of addition shall be announced and acknowledged by an SRO prior to initiation. The intended results shall be discussed with the SRO, as well as the actual results when the evolution is complete. The actual ' volume added and rate shall be logged.ca C E. During blender operations, the RO shall continuously monitor the makeup rate, volume; ( and expected results.c.t Ill. INITIAL CONDITIONS A. Charging and letdown flow has been established. B. The boric acid tanks contain sufficient boric acid solution to perform a boration operation without reducing the 1.nventory below the amount required in Tech. Specs. C. '[2CHS*P22A(B)], Boric Acid Transfer Pump, is in Auto and aligned to supply boric acid to the blender from an operable Boric Acid Tank, [2CHS'TK21 A(B)]. D. Sufficient holdup tank volume is available to receive the reactor coolant displaced l during dilution. E. A minimum flow rate of 2: 3000 GPM shall be maintained through the reactor core l whenever a boron dilution is being performed by verifying that either a RCP is operving or a RHR Pump is in service. (Tech Spec 4.1.1.3,4.9.8.1.b) l 'O i
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Bssvrr Valley Powar Stition Unit 2. 2OM-7.4.N Chemical and Volume Control System issue 4 Revision 3 Page N 2 of 6
- Operating Procedures '
V' - BLENDER MANUAL MAKEUP OPERATIONS g
- lV. INSTRUCTIONS ,
Note: If in Modes 1,2 or 3,it is not required to copy this procedure and route the completed cop'y to Document Control. A. Manual' Blended Makeug
- 1. Obtain the reactor coolant system boron concentration from the last Chemists
- analysis. ,. i
- 2. Place the Boric Acid Makeup Blender Control switch in the Stop positler,. ',BB-A) 3, If in Mode 4,5, or 6, align PG water to the blender by unlocking and openiny one - ,
of the following valves:
- a. [2CHS-37], Primary water To Blender Isol Aux Bldg 710'
- b. [2CHS-828], Boron Dilution Limiting Orifice Isol, Aux Bldg 710'
- c. . [2CHS-91], Pri Wtr To Blender Isol, Aux Bldg 710' l
- 4. Place the makeup Mode Selector switch in the Manual position. (BB-A) l O
Q Note: 1% of VCT level equals approximately 16 gals.
- 5. Set the Total Makeup From Blender Flow Totalizer, to the desired total volume in gallons of makeup water to be added. (BB-A)
- 6. . Adjust [2CHS*FCV113A], Boric Acid To Boric Acid Blender, to the desired setting as follows:
. a. Determine Boric Acid Flow from the following calculation:
a= Desired blender outlet concentration. b= Desired blender total flow. (Normally 75 gpm) c= Actual boric acid supply concentration. -(In service BA storage tank) a b Boric Acid Flow =
- b. Set [2CHS'FCV113A] as follows:
Pot Setting = 0 #IC #CI ## 4 gpm
- 7. Adjust [2CHS* HIC 168], Blender Total Flow Auto Setpoint, to the blender total flow used in Step 'A.6.
esire w Rate Pot Setting = 16 gpm
- 8. Adjust [2CHS-FCV114A] pot setting to the same as [2CHS* HIC 168].
Beaver Vallay Power Station Unit 2 2OM-7.4.N Chemical and Volume Control System issue 4 Revision 3
- Operating Procedures . Page N 3 of 6 BLENDER MANUAL M AKEUP OPER ATIONS
- 9. Set Boric Acid Flow To Blender Flow Totalizer, to the total volume in gallons of boric acid to be added from the following equation:
Total Makup Volume B.A. Volu me = B.A. Flow X TMalMa W N
- 10. Verify the inservice Boric Acid Transfer Pump is in Auto. (BB-A)
CAUTION: CONTINUOUSLY MONITOR VCT LEVEL, TAVG AND ROD MOTION WHILE OPER ATING THE BLENDER IN M ANUAL. TERMINATE THE BLENDING OPERATION IF TRENDS ARE ABNORM AL. Note: The makeup operation may be terminated at any time by placing the Boric Acid Makeup Control switch in the Stop position. ' 11. Open [2CHS*FCV113B], Boric Acid Blender Disch To Chg Pumps. (BB-A)
- 12. Prior to the start of AND at least once every hour during a reduction in the RCS boron concentration: (Tech. Spec. 4.1.1.3,4.9.8.1.b) (N/A if raising or maintaining f.., RCS boron concentration)
- a. Verify that either a reactor coolant pump is operating in an unisolated loop -
OR that the RHR pump is operating with 2: 3000 gpm flow through the core.
- b. Record the results of this check in the Daily Journal. ,
- 13. To initiate makeup, place the Boric Acid Makeup Control switch to the Start position. (BB-A)
,14. Verify the Boric Acid Transfer Pump that is in auto is running.(BB-A) l 15. Verify proper operation at recorder [2CHS-FR113];(VB-A)
- a. Boric Acid To Blender
- b. Total M/U Flow From Blender
- 16. If reducing RCS boron concentration, Operate pressurizer heaters
! [2RCS*H2A,B,C,D,E], PRZR Heaters Group A, B, C, D, E, to automatically initiate l spray as required to equalize boron concentration between coolant loops and pressurizer to within 50 ppm. (Otherwise N/A)
- 17. When desired makeup is completed, stop the makeup operation by placing Boric j
' Acid Makeup Control switch to the Stop position. (BB-A) .
- a. If in Mode 4,5, or 6 Record the time the makeup was stopped in the Daily Journal. (T.S. 4.1.2.9.a). l r i
(% ~
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Beevar Vallsy Power Stetion . Unit 2 20M-7.4.N Chemical and Volume Control System , issue 4 Revision 3 4 _ Operating Procedures ' Page N 4 of 6 _I BLENDER M ANUAL MAKEUP OPERATIONS g
- 18. If in Mode 4,5, or 6, within 15 minutes after the completion of the makeup in Step A.17, close the following valve that was previously locked closed AND Record the .
time the valve was closed in the Daily Journal. (T.S. 4.1.2.9.a). (N/A valves not previously locked).
- a. [2CHS-37], Primary Water To Blender Isol, Aux Bldg 710' (1) /
1 initial / Date (2)__ / - Initial / Date j
- b. [2CHS-828], Boron Dilution Limiting Orifice Isol, Aux Bldg 710'. ;
(1) / initial / Date (2) / ; Initial / Date
- c. [2CHS-91], Prl Wtr To Blender Isol, Aux Bldg 710'. ;
(1) / Initial / Date .i (2) I i O initial / Date
- 19. If in Mode 4,5, or 6, within 15 minutes after the completion of the makeup in Step A.17, lock the following valves that were previously locked closed AND Record the time the valve was locked in the Daily Journal. (T.S. 4.1.2.9.a). (N/A valves not previously locked).
. a. [2CHS-37], Primary Water To Blender Isol, Aux Bldg 710'.
(1) / Initial / Date (2) / . Initial / Date
- b. [2CHS-828], Baron Dilution Limiting Orifice Isol, Aux Bldg 710'.
(1) / Initial / Date (2) / InitialI Date
- c. ' [2CHS-91], Pri Wtr To Blender Isol, Aux Bldg 710'.
4 (1) / Initiall Date O (2) /
- k' Initial / Date
- 20. If in Mode 1,2, or 3, place the makeup control system in automatic in accordance with 2OM-7.4.J. " Blender Automatic Makeup Operations".
-,n v -,r ,.n> ,- -- - ,
Bsivtr Valley Pownr Station Unit 2 2OM-7.4.N Chsmical and Volumn Control System issue 4 Revision 3 Operating Procedures . Page N 5 of 6 O ! BLENDER MANUAL MAKEUP OPERATIONS (]
- 21. If. pressurizer heaters were operated in Step A.16. THEN return the following control switches to the Normal System Arrangement positions as listed AND document with independent verification in the Daily Journal (Otherwise N/A):
(BB-B)
- a. [2RCS*H2A], Przr Heaters Backup Group A, control switch to AUTC.
- b. [2RCS*H2B], Przr Heaters Backup Group B, control switch to AUTO.
- c. [2RCS-H2C], Przr Heaters Backup Group C, control switch to AFTER-ON.
- d. [2RCS*H2D], Przr Heaters Backup Graup D, control switch to AUTO.
- e. [2RCS*H2E], Przr Heaters Backup Group E, control switch to AUTO.
Performed By V- ' ied By l u , viewed By Date NSSIANSS Route the completed copy of this procedure to Document Control via the Operations clerk's dally transmittals. '/ O. W
~, ..
Bssvar Vallsy Powar StEtion Unit 2 20M-7.A N Chemical and Volume Control System issue 4 Revision 3
.. Operating Procedures Page N 6 of 6
( O)' BLENDER MANUAL MAKEUP OPERATIONS i V. REFERENCES A. TECHNICAL SPECIFICATIONS
- 1. BVPS-2 T.S. 4.1.1.3
- 2. BVPS-2 T.S. 4.1.2.9.a
- 3. BVPS-2 T.S. 4.9.8.1.b l B. UPDATED SAFETY ANALYSIS REPORT <
NONE C. COMMITMENTS
- 1. Operations 1996 INPO Corrective Action Plan, Finding OP.2-2, item 2.
D. ADMINISTRATIVE - NONE E. VENDOR INFORMATION NONE C. F. DRAWINGS 10080 RM-407-2, VOND Charging Sys VCT And Make-Up 1. G. OPER ATING MANUAL
- 1. 2OM 7.1, Chemical And Volume Control System, Description
- 2. 2OM 7.2, Precautions, Limitations and Setpoints
, 3. 2OM-7.4.J. Blender Automatic Makeup Operations H. PLANT MODIFICATION NONE I. OTHER
- 1. OMDR 2-91-0472 (Rev 0)
- 2. OMCR 2-96-0284, T.S. Amend. 78, OMCR 2-96-0051 (Rev 1)
- 3. OMCR 2-97-0126 (Rev. 2)
- 4. OMCR 2-97-0616; Added step with reference to Tech Spec 4.1.1.3 and 4.9.8.1.b if reducing RCS boron concentration; Added steps to operate PRZR heaters if reducing RCS boron concentration and to return to NSA; Added note concerning copying procedure (Rev. 3)
O v
i- ' l k RTL #A5.640U BEAVER VALLEY JOB PERFORMANCE MEASURE EVALUATOR COVER SHEET l, JPM Number: 2CR-NPZR Rev: 0 System #: 011 !i l JPM
Title:
Respond to Plant Annunciators K/A
Reference:
011A2.11 3.4/3.6 Task ID #:011BBB0101 l JPM Application: E Requal X Initial Exam OTraining i i Evaluation Method LOCATION TYPE { j Perform O Plant Site O Training . { Simulate O Simulator O Annual Requal. Exam ~ j O Classroom O OJT , O Initial Operator Exam l j Administered By: Other: I j BV-T i
" j f
Other: E I i Evaluation Results Performer: Name: Employee No: b Results O SAT Time (minutes) O UNSAT* Allotted: 15 Actual: Time Critical: Yes S No Administrative JPM O Paulted O
- Comments (Required for UNSAT Evaluation):
. , .~
Evaluation Results O Check here if same as above Observer 1: Name: Employee No: Observer 2: Name Employee No: Observer 3: Name Employee No: Observer 4: Name Employee No: Time (minutes) Results Question ID Allotted Actual SAT UNSAT* Question #1 O O Employee No: Question #2 O Employee No:
- Comments (Required for UNSAT Evaluation):
Evaluator (Print): Organization: Evaluator Signature Date: After Val
RTL #A5.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE
." CANDIDATE DIRECTION SHEET V
- THIS SHEET TO BE GIVEN TO CANDIDATE
' Read:
Task: lRespondtoPlantAnnunciators INITIAL' CONDITIONS: lTheplantis.inMode1.~Allsystemsare- - in NSA. t INIT. CUE: You are the Reactor operator, and'you are to ' respond to any annunciators received. i At this. time, ask the' evaluator any questions you have on this
/(,,g JPM.
-When-satisfied that-you understand-the assigned task, announce "I am now beginning the JPM".
Simulate performance or perform as directed the required task. Point'to any indicator or component you verify or check and , announce your observations.
- After determining the Task has been met, announce "I have completed'the JPM". Then hand back this sheet to the
-evaluator. ,
( L)\ After Val g- r,. 3 -,y, y e
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I l. I RlL #A5.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE EVALUATOR DIRECTION SHEET [V] ( JPM NUMBER: 2CR-NPZR . l JPM TITLE: Respond to Plant Annunciators
. TASK STAN.. PZR level transmitter 461 is controlling PZR level in automatic..
RECOMMENDED . STARTING. LOCATION: CONTROL ROOM ,
.i DIRECTIONS: You are to simulate (perform) the task Respond to Plant Annunciators INIT. CONDITIONS: The plant is in Mode 1. All systems are in NSA.
1 INIT. CUE: You are the Reactor operator, an,d you are ,
, to respond to any annunciators received.- i ;( ]
1
REFERENCES:
20M-6.4.IF issue 4 rev. 4 TOOLS:. None HANDOUT: 20M-6.4.IF issue 4 rev. 4 4 i O. L( 1
.v After Val
,, r RTL-'#A5.635.J
(
'*
- THIS SHEET TO BE GIVEN TO CANDIDATE
- BVPS' JOB PERFORMANCE MEASURE ORAL QUESTION #1 Using the PZR level Hot and Cold calibration curves, explain t'
why it is necessary to have Hot and Cold Channels,.as opposed to having one transmitter calibrated for the full range of t
. temperature and pressure.. .
l 1 l l l i l I i I i [h* i ll After Val-
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.. p RTL #AS.635.J BVPS JOB PERFORMANCE MEASURE f\ ORAL QUESTION #1 Using the PZR level Hot and Cold calibration curves, explain why it is necessary to have Hot and Cold Channels, as opposed to having one transmitter calibrated for the full range of temperature and pressure. 1 ANSWER: Necessary to have two since with only one, the ' large density change over the spectrum of cold atmospheric pressure to hot full power pressure would leave areas of the transmitter'with large inaccuracies. l TIME 5 minutes
' ALLOTTED:
KSA #: 011 K4.03 2.9 .i
' _j - REF: Pressurizer Tank Curves of Tank Curve Book.
- COMMENTS: j l
[~'\ . 8
. V) l l
- . After Val l
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l 1 'RTL #A5.635.J e
- THIS SHEET TO BE GIVEN TO CANDIDATE *
!I l- ! ^ BVPS JOB PERFORMANCE MEASURE , t !' ORAL-QUESTION #2 i
- . The plant is operating at HZP Mode 3 with PZR level control in fi -Manual. PZR level channel 461 is reading 50%. How will l
indicated PZR level respond to a leak in the reference leg that' ] slowly empties the reference leg? . Explain- .; 1 4 ? i J f;- f i i-1 dv After Val
-= - ._
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RTL #AS.635.J BVPS JOB PERFORMANCE MEASURE l f'~g ORAL QUESTION #2
\'j The plant is operating at HZP Mode 3 with PZR level control in l Manual. PZR level channel 461 is reading 50%. How will indicated PZR level respond to a leak in the reference leg that i slowly empties the reference leg? Explain.
1 ANSWER: Indicated level will slowly rise. ' Transmitters are calibrated such that when AP is zero, the pressurizer indicates full. Since the reference leg is the high side pressure, as the , leak empties, reference leg AP will drop and
-indicated level' will rise TIME 4 minutes ALLOTTED:
KSA #: 028 AKl.01 3.1 > i l 1,- REF: Theory (
)
1 l COMMENTS:
)
~
\
1
'?
\
After Val l l
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RTL #A5.635.J 1
- (~'N
\~ NUMBER TITLE 2CR-NPZR Respond to Plant Annunciators l
STEP STANDARD l (Indicate "S" for Sat. or "U" j
- ("C" denotes critical step) for Unsat.)'
l
. Start time:
EVALUATOR NOTE: The , candidate may first respond to individual ARPs before eventually recognizing the symptoms for entry.into 20M-6.4.IF. f- Candidate locates ( procedure 20M-6.4.IF.
-p t.
l1. . Candidate identifies a 1. Candidate identifies , level channel has level channel i failed. [2RCS*LT459] has l failed'and. refers to Attachment 1 . COMMENTS: i-fim
'l ): I
- (/
l' 4 ! Page 1.of 9 After Val
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- r
.RTL #AS.635.J
/~
?
('A- NUMBER- TITLE 2CR-NPZR Respond to Plant Annunciators STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for'Unsat.)
- 2. Candidate. identifies 2. Candidate identifies level channel which level channel has failed, and.how it has [2RCS*LT459) has failed. failed, it has failed low.
l COMMENTS: 3.C Place PRZR Level 3.C Candidate places PRZR
.f control Channel Level control Channel I selector switch to II & selector switch to II III position. .& III position.
l COMMENTS:
- 4. Ensure.PRZR level 4. Candidate places recorder-is selected to PRZR 1.evel recorder controlling channel. channel III.
COMMENTS: O
'% )
Page 2 of 9 After Val
- RTL #A5.63'5.J ,
- g.
. (A -- NUMBER TITLE- , 2CR-NPZR Respond to Plant Annunciators r STEP STANDARD (Indicate "S" for Sat, or "U" for Unsat.)
-("C" denotes critical step) .
5.~ Ensure adequate-Makeup 5. Candidate checks to VCT blender set in automatic. COMMENTS: A- - 6.- Ensure PZR Heaters 6.1 Candidate checks to 1 return to normal ensure PZR Heaters h' ): operation. return to normal operation. COMMENTS: , l EVALUATOR CUE: As your supervisor, I desire heater groups D, and C to be energized. 1 i l
/^s i
.Page 3 of 9 After Val
RTL #AS.635.J
.f%
NUMBER TITLE 2CR-NPZR Respond to Plant Annunciators STEP. STANDARD (Indicate "S"'for Sat. or "U" ("C" denotes critical step) for Unsat.) 6.2 Candidate places CS for heater groups D and C to CLOSE Verifies red lights LIT
', tiftes_ green lights "9T LIT COMMENTS:
- 7. Ensure [2CHS*FCV122) is 7. Candidate checks Ic repositioned to desired (2CHS*FCV12.2] is serpoint. repositioned to desired setpoint.
COMMENTS: Page 4 of 9 After Val
RTL #A5.635.J-
/~~N
\ NUMBER TITLE 2CR-NPZR Respond to Plant Annunciators STEP STANDARD (Indicate "S" for Sat. or "U"
("C" denotes critical step) for Unsat.) . 8.C' Restore letdown 8.1.C Candidate places A/M station for Charging
. pump disch'. Flow control V1v
[2CHS*FCV122]'to MAN (BB-A) Verifles MAN light LIT Verifies AUTO light 1 NOT LIT ,
, (*
COMMENTS: 8.2.C Candidate adjusts position of Charging pump disch. Flow
-control Vlv.
[2CHS*FCV122]_to achieve-30-50 gpm as indicated on [2CHS-FI122A] (VB-A) COMMENTS:
- \.
Page 5 of 9 After Val
RTL #AS.635.J f 's
~ k. NUMBER TITLE ,
2CR-NPZR- Respond to Plant Annunciators STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.) 8.3 Candidate checks Letdown orifices 21, 23, & 22 isol (2CHS*AOV200A,B,& C] CLOSED Verifies green light LIT Verifies red light NOT LIT - 3 COMMENTS: 8.4.C Candidate places CS for Regenerative Heat Exch Letdown Inlet Vlv[2CHS*LCV460A] to OPEN (BB-B) Verifies red light LIT 4 Verifies green light NOT LIT COMMENTS: l i i (_/ 1 Page 6 of 9 After Val I...> .. .. ...r ..
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i- . RTL #AS.635.J
'C\
(\_/ NUMBER TITLE l 2CR-NPZR Respond to Plant Annunciators l l 1 I l STEP STANDARD l (Indicate "S" for Sat. or "U" l ("C" denotes critical step) for Unsat.) , 1
~
8.5.C Candidate places Non- l Regenerative HX Disch. Press Control Vlv [2CHS*PCV145] A/M station to MAN and adjusts to 50% demand. Verifies MAN light LIT Verifies AUTO light l NOT LIT i em I J' Uses raise. lower PB to (' adjust demand to 50% COMMENTS: EVALUATOR CUE: As your supervisor, I desire a 60 gpm and a 45 gpm orifice to be placed in service at
.this time. .
I ['si
-t RJ l
Page 7 of 9 After Val
- ,_ .- . - - . .. -.. . . _ . . . . . . ~ . ~ - . . -- - - . _ . ,.
RTL'/A5.635.J , If}
'V. NUMBER TITLE 2CR-NPZR Respond to Plant Annunciators STEP STANDARD (Indicate "S" for Sat. or "U"
("C" denotes critical step) for Unsat.) 8.6.C Candidate places CS for Letdown orifices 21, 23 or 22, isol (2CHS*AOV200A&BorC) to OPEN Verifies red lights LIT Verifies green light ' NOT LIT f e'} V l COMMENTS: 1 l l
. 8.7.C Candidate adjusts Non- ~
)
Regenerative HX Disch. -! Press Control Vlv , [2CHS*PCV145] A/M l station to achieve a backpressure of 260 j psig as indicated on [2CHS*PI145). (BB-A) l COMMENTS: ! l A '(.'%Jl.
> s s
Page 8 of 9 After Val
- ,. ~ ~ - - . - -- .-- - - . . - . . . . - -. . . . ~ . . . . .
RTL #A5.635.J t
/
((j NUMBER TITLE ; 2CR-NPZR Respond to Plant Annunciators STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.) - 8.8. Candidate places Non-Regenerative HX Disch. ' Press Control Vlv [2CHS*PCV145] A/M < station to AUTO. COMMENTS: A EVALUATOR CUE: For the j O - purposes of this JPM it is ! NOT necessary to refer to ; Tech Specs or initiate an MWR. COMMENTS: Stop Time: i-Ylh q iV) l t Page 9 of 9 After Val
........_,,.-...-~.~~_..........-..~.-~,~....~.c-. . . . . ~ . - - _ . . . ~ .
k Record Type #A9.3000 0 : DUQUESNE LIGHT COMPANY Beaver Valley Power Station e Unit 2 FOR TRAINJNG USE ONLY
' ~
l 20M-6.4.lF j INSTRUMENT FA1 LURE PROCEDURE
- [}
((f' I l
- Issue 4 Revision 4 Date Pages issued Effective Date Prepared by M. P; Flynn 12/07/96 IF1 thru IF40 DEC 1 6 1996 l Date Validated by Date Reviewed by 12/07/96 ]
C. O'Neill ryg Date Approved b Date OSC Meeting No.
. Non-Intent 12/07/96 g g / [yp Bn /284e n
U] @@ M DDBW
@ M @BBV 2
WTG' AE330C OPERATING MANUAL CHANGE NOTICE 1/2OM-48.2.B-2 Circle Applicabl3 Unit I Uni *te) l Unit 2 (Blue); Unit 1/2 (Pink) Chapter, Section & Procedure ?_ Q FA -lo.'\ ,T F A%ch , 2. i Issue '\ Rev. '\ Annunciator Window Intent Change? YES M NO (if NQ, Perform and attach a Non-intent Verircaten form) Does this change conflict with the UFSAR (Either Figures OR Text)f 5 l lYES l><fNO
- (if H,s, perform a safety Evaluaten (10CFR50.59) screenmg in accordance with NPDAP 8.18) j Does this change affect a VONDf5 R YES I><1NO (if H1, initiate a VCN) '
Does this OMCN change an NSAf5 l lYES l><lNO. ! (If Hi, perform a safety Evaluation (10CFR50.59) screerung in accordance with NPDAP 8.18) Is this change in response to, OR changes a Regulatory or DLC Commitment? I lYES l'><1 NO l' (if H.s., identify the commdment document and basis) , This is Page 1 of 2> Pages RECORD ALL OF THE ATTACHED PAGE l 2_O M - 6,4 .T F A h e M m e A t ~2_ b.wa ' ri ( % i REASON FOR CHANGE: Wdw E \ eb$ ne es ~T.S . S.E \.\ MAe EA-\ ba ! R ad \D . %eu\c\ ' a\so edecenef_ W% I Co7 6M _ ORIGINATOR ( k {.5 - 7,rz.( Employee No. cw .qq DATE OsIGNATURE Pl \NT STAFF
- M MBER b%kW. - slGNATURE ns.c Employee No.
1 % DATE
- SPED ENGINEER REQUIRED FOR alt. INTENT CHANGES TO OST's or other procedure that b UNIT 1 SRO d f.x
'\ GNATU Employee No. DATE implements a Tech Spec UNIT 2 SRO .
[ J 253S 9-F-? 7 Survelitance
. slGNATURE Employee No. DATE OSC REVIEW BV-OSC- COMMENT M 47 s 9M v/97 MEETING No. DATE Unreviewed Safety Question l jYES @ No Appr0 val Recommended @ YES R NO
[ Approved f-29-99 l l Disapproved DATE DATE e Y General stanager Nuclest Ops a 3WO Employee No. General Manager Nuclear Ops Employee No.
. NOTE: . INTENT changes REQUIRE GMNO approval PRIOR to implementation.
NON-INTENT changes REQUIRE GMNO approval within 14 days of Effective Date. 7 Does this OMCN Change an Operator Aid? U YES N The revision used for this OMCN is current. YES Does this OMCN Change a Station Log?. [_j YES NO Prior to assignment of the OMCN number, this form has been administratively reviewed for applicable form co leteness in accordance with the instructions on the back.
-/9- 9'7 /OC() Number: OMCN- A -
M bd6.
') Effective Date Time, This section completed by; k NM g O d d.v C/M/P -
NM Employee No ($ichature Revision 11
=
Beaver Valley Power Station Unit 2 20M-6.4.lF Reactor Coolant System issue 4 Revision 4 Operating Procedure Page IF 1 of 40 - kj INSTRUMENT FAILURE PROCEDURE
- 1. PURPOSE This procedure provides the information and instractions necessary to recover from a process instrument failure that affects certain reactor control system control and functions functions.
II. PRECAUTIONS & LIMITATIONS A. Following the failure of a process instrument that provides a reactor trip or si ety injection signal the affected bistable must be placed in a tripped condition. A reactor trip or safety injection will then occur upon receipt of a subsequent reactor trip or safety injection signal from the same parameter. Ill. INITIAL CONDITIONS A'. A process instrument has failed as determined by one of the following alarm response procedures:
- 1. 20M-6.4.AAR, Pressurizer Level High
- 2. 20M-6.4.AAO, Pressurizer Control Heater Group Trouble
,~. 3. 2OM-6.4.AAW, Pr.essurizer Backup Heater Group Auto-Close/ Trip
- 4. 2OM-6.4.AAK, Pressurizer Control Level High/ Low
\
- 5. 20M-6.4.AAL, Pressurizer Control Level Deviation High/ Low
- 6. 20M-6.4.AAT, Pressurizer Press High/ Low ;
- 7. 20M-6.4.AAN, Pressurizer Control Press Deviation High/ Low
- 8. 20M-6.4.AAM, Pressurizer Control Press High/ Low
- 9. 2OM-6.4.AAU, Pressurizer Control Press High Pwr Rif Act
- 10. 20M-6.4.AAF, Reactor Coolant Loop Flow Low
- 11. 20M-1.4.AAT, Loop Txyc Deviation
- 12. 2OM-1.4.AAU, Loop AT Deviation
- 13. 20M-1.4. AAV, T,vc Deviation from Tur
- 14. 20M-1.4.AAW, Loop Overpower AT
- 15. 20M-1.4.AAX, Loop Overpower AT Auto-Turb Rnbk Block Rod W/D
- 16. 20M-1.4. AAY, Loop T,vc High
- 17. 2OM-1.4.AAZ, Loop Overtemperature AT
- 18. 20M-1.4.ABA, Loop Overtemp AT Auto Turb Rn'
- 531ock Rod W/D
,, 3 f )
- 19. 20M-1.4.ACA, Loop Tavg Low-Low
(,,/ j
, J
m._ _. . .. _ . . - _ . _ . . . _ _ _ _ . . _ ___ ._.._.. __ _._ _ .__ _ __.._..._... __ Beaver Valley Power Station Unit 2 2OM-6.4.lF Reactor Coolant System issue 4 Revision 4 . , Operating Procedure Page IF 2 of 40 ' INSTRUMENT FAILURE PROCEDURE IV. INSTRUCTIONS A. If [2RCS*LT459,460 or 461] has failed as determined by.o.ne of the alarm response procedures, THEN refer to Attachment 1. B. If [2RCS*PT444,445,455,456, or 457] has failed as determined by one of the alarm
- response procedures, THEN refer to Attachment 2.
C. If [2RCS*FT414,415,416,424,425,426,434,435, or 436] has failed as determined by the alarm response procedure THEN refer tu Attachment 3. D.- If [2RCS"TE412B1, B2, 83, D] OR [2RCS*TE422B1, B2,83, D] OR [2RCS*TE43281, B2, 83, D] has failed as determined by.one of the alarm response procedures, THEN refer to ttachment 4. t 1 i l' [ ~. I p LO i 4 e e
_. _ _ _ _ . . _ . - - - ~ _ _ _ . . . _
. Baaver Valley Power Station - Unit 2 2O M-6.4.lF - t Rerctor Coolant System- Issue 4 Revision 4-
. Operating Procedure -
^
Page IF 3 of- 40 : f~ ( ' f INSTRUMENT FAILURE PROCEDURE i
~
M V. REFERENCES , Note: . The attachments have references that are specific to the individual attachment. A. ' TECHNICAL SPECIFICATIONS
< NONE I B. UPDATED FINAL SAFETY ANALYSIS REPORT 4 1
NONE C. COMMITMENTS .) NONE D.- ADMINISTR ATIVE - 1 NONE l 1
. E. VENDOR INFORMATION NONE L ,^-4 F. DRAWINGS
.; ( I
%) NONE G. OPERATING MANUAL
- 1. 2OM-6.4.AAR, Pressurizer Level High
- 2. 2OM-6.4.AAK, Pressurizer Control Level High/ Low
- 3. 2OM-6.4.AAL, Pressurizer Control Level Deviation High/ Low
- 4. 20M-6.4.AAO, Pressurizer Control Heater Group Trouble 1
- 5. 2OM-6.4.AAW. Pressurizer Backup Heater Group Auto-Close/ Trip
- 6. 2OM-6.4.AAT, Pressurizer Press High/ Low
- 7. : 2OM-6.4.AAM. Pressurizer Control Press High/ Low i 8.- 20M-6.4.AAN, Pressurizer Control Press Deviation High/ Low
- 9. 2OM-6.4.AAU Pressurizer Control Press High Power Rif Act
- 10. -20M-6.4.AAF. Reactor Coolant Loop Flow Low
- 11. 20M-1.4.AAT, Loop T,vc Deviation
' 12. 20M-1.4.AAU, Loop AT Deviation
- 13. 20M 1.4. AAV, T AVG Deviation from Tac, 4 j 14. 2OM-1.4.AAW, Loop Overpower AT
- 15. 20M-1.4.AAX, Loop Overpower AT Auto Turb Rnbk Block Rod W/D
- 16. 2OM-1.4.AAY, Loop T,ve High
/
s
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A
. Beaver Valley Power Station Unit 2 20M-6.4.lF
' Reactor Coolant System ~ Issue 4 Revision 4 ,
. Operating Procedure . Page IF 4 of 40 .
f,
) ,
INSTRUMENT FAILURE PROCEDURE ,
- 17. 20M-1.4.AAZ, Loop Overtemp AT f
- 18. 2OM-1,4.ABA, Loop Overtemperature AT Auto Turb Robk Block Rod W/D 19; 20M-1.4.ACA, Loop Tavg Low-Low 'j Hi ' PLANT MODIFICATIONS NONE
' l. OTHER' ;
NONE:-
.i.
l
- I l
l 1
. .~ +
O -}
^
n l I J I .' l s l. t ^i
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+ .' 4
. + . - - - - , , . - , .- ..a. - , . - . -- . n r
Beaver Valley Power Station Unit 2 2OM-6.4.lF Reactor Coolant System issue 4 Ravision 4 , Operating Procedure Page IF S of 40 INSTRUMENT FAILURE PROCEDURE ATTACHMENT 1 [2RCS*LT459 (460) (46t)] -
- 1. OPERATOR RESPONSESISYSTEM RESTORATION Note:
- Control Responses will result only if the failure occurs in a channel selected-for control.
+ Failure of any channel will require protection system input determination and possible bistable tripping.
A. Identify which channel has failed and how it has failed by comparing [2RCS*LT459A, 460, and 461], PRZR Level Channel 1,2, and 3 meter indications, on BB-B. B. If [2RCS*LT459] has failed, perform the following:
; 1. Place PRZR Level Control Channel Selector to position ll & 111.
,s
- 2. Ensure PRZR Level Recorder Selector is positioned to record controlling level l
channel.
- 3. - If [2RCS*LT459] has failed high, perform the following;
- a. Ensure PRZR Heaters Control Groups A and D are off if all other conditions allow. )
. b. Ensure PRZR Heaters Backup Groups B and E are off if all other conditions allow.
- c. Ensure [2CHS*FCV122], Charging Pumps Disch Flow Control Viv, is repositioned to the desired setpoint.
- 4. If [2RCS'LT459] has failed low, perform the following;
- a. Ensure there is adequate makeup to the VCT.
- b. Ensure PRZR Heaters Control Groups A and D have returned to normal operation OR, if desired, manually energize the heaters to restore pressure.
- c. ' Ensure PRZR Heaters Backup Groups B and E have returned to normal operation OR, if desired, manually energize the heaters to restore pressure.
- d. As necessary, close PRZR Heaters Control Group C Breaker, to energize Group C heaters.
O (i e. Ensure [2CHS*FCV122], Charging Pumps Disch Flow Control Viv, is repositioned to the desired setpoints. ATT ACHMENT 1
Beaver Valley Power Station Unit 2 2OM-6.4.lF
- Reactor Coolant System issue 4 Revision 4 Operating Procedure Page IF 6 of 40 INSTRUMENT FAILURE PROCEDURE ,
- f. Restore letdown as follows:
Note: Letdown domineralizer capacity should NOT be exceeded. . 1) Throttle [2CHS*FCV122], Charging Pumps Disch. Flow Control Viv (BB-A) to establish a flowrate of 30 to 50 gpm as indicated on [2CHS-Fl122A], Charging Flow (VB-A).
- 2) Ensure [2CHS*AOV200A, B .and C], Letdown Orifices 21,23, and 22
! Isols, are closed.
- 3) Open [2CHS*LCV460A and 460B], Regenerative Heat Exch Letdown intet Vivs, by placing the control switches on BB-B to OPEN.
- 4) Place [2CHS*PCV-145], Non Regen HX Disch Press Control Viv, in MANUAL AND adjust to 50% demand. .
- 5) After [2CHS*LCV460A and B] are open, open [2CHS*AOV200A, B and C],
Letdown Orifice 21,23,22 Isols, as desired by placing the control switch on BB-B to OPEN. ; I
- 6) Adjust [2CHS*PCV145] to obtain 260 psig backpressure as indicated on l
[2CHS*Pl145], Letdown Press, THEN, if desired, place [2CHS*PCV145] il l
' AUTO. -
- g. - Proceed to Step E.
C, If [2RCS*LT460] has failed, perform the following: !
- 1. Place PRZR Level Control Channel Selector to position I & Ill.
- 2. Ensure PRZR Level Recorder Selector is positioned to record controlling level channel.
- 3. Il[2RCS*LT460] has failed high, perform the following:
- a. Proceed to Step E.
- 4. If [2RCS*LT460] has failed low, perform the following:
- a. Ensure there is adequate makeup to the VCT.
- b. Ensure PRZR Heaters Control Groups A and D have returned to normal operation OR,if desired, manually energize the heaters to restore pressure.
- c. Ensure PRZR Heaters Backup Groups B and E have returned to normal operation OR,if desired, manually energize the heaters to restore pressure.
f d. As necessary, close PRZR Heaters Control Group C Breaker, to energize Group C heaters.
- e. Ensure [2CHS*FCV122], Charging Pumps Disch Flow Control Viv, is /
j i repositioned to the desired setpoint.
%* ATTACHMENT 1
Beaver Valley Power Station Unit 2 20M-6.4.lF Reactor Coolant System Issue 4 Revision 4 Operating Procedure Page IF 7 of 40 INSTRUMENT FAILURE PROCEDURE
- f. Restore letdown as follows:
Note: Letdown demineralizer capacity should NOT be exceeded.
- 1) Throttle [2CHS*FCV122), Charging Pumps Disch Flow Control Viv (BB-A) to establish a flowrate of 30 to 50 gpm as indicated on [2CHS-Fl122A],
Charging Flow (VB-A).
- 2) Ensure [2CHS*AOV200A, B and C], Letdown Orifices 21,23, and 22 Isols are closed.
- 3) Open [2CHS*LCV460A and 460B], Regenerative Heat Excn Leidown inlet Vivs, by placing the control switches on BB-B to OPEN.
- 4) Place [2CHS*PCV145], Non Regen HX Disch Press Control Viv, in MANUAL AND adjust to 50% demand.
- 5) After [2CHS*LCV460A and B] are open, open [2CHS* AOV200A, B and C],
Letdown Orifice 21,23, and 22 Isoli;, as desired by placing the control switch on BB-B to OPEN.
- 6) Adjust [2CHS*PCV145] to obtain 260 psig backpressure as indicated on
[, [2CHS-Pl145], Letdown Press, THEN, if desired, place [2CHS*PCV145] in
\ AUTO.
- g. Proceed to Step E.
D. If [2RCF 'LT461] has failed, perform the following:
- 1. Ensure PRZR Level Control Channel Selector is in position I & 11.
. 2. Ensure PRZR Level Recorder Selector is positioned to record controlling level channel.
- 3. If PRZR Level Ghannel Selector was in position 11 & 111 THEN go to Step B AND perform the applicable steps.
~
4.- If PRZR Level Channel Selector was in position I & Ill, THEN go to Step C AND perform the applicable steps. E. Refer to the following Technical Specifications to trip any required bistables by placing them in test. Note:
- Table 1 of this Attachment lists the bistables and locations.
+ Key 117 or 118 is needed to unlock the protection racks.
,J 1. T.S.~3.3.11 and Table 3.3-1 Item 11. Reactor Trip Instrumentation, Applicable
.l Modes 1 & 2 > P-7
- 2. T.S. 3.3.3.5 and Table 3.3-9, item 8. Remote Shutdown Instrumentation. Applicable Modes 1,2, & 3.
ATTACHMENT 1
~
- Beaver Valley Power Station - Unit 2 20M-6.4.lF
- Reactor Coolant System - Issue 4 Revision 4 Operating Procedure Page IF 8 of 40 ,
N-
'NSTRUMENT l FAILURE PROCEDURE -i I
[ ,
- 3. T.S. 3.3.3.8 and Table 3.3-11,~ ltem .1, Accident Monitoring Instrumentation, '
Applicable Modes 1,2, & 3. .i F.. - Repairs
- 1. !nitiate an MWR to investigate the cause and repair the failed channel.
l 4 l l 1 I .. 'g e e Y. V I L ': ATTACHMENT 1 _ _ _ _ _ _ _ . _ _ . s._ _ _ _ . _ _ _ - _. __ _- --e., aro- .we , .- -, . - - - y + ,
, 4 .
- B aver Valley Pc, war Station Unit 2 2OM-6.4.lF
- Reactor Coolant Systam issue 4 Revision 4 Operating Procedure ; 'Page IF 9 of 40 - 1 s, L INSTRUMENT FAILURE PROCEDURE:
D)' A . . l II. RESPONSES
- A. Plant Responses.
i
'1.1 Redundant indications confirm a high or low failure of a pressurizer level channel'.
;2. "The following are possible plant response to a low failure of a level transmitter: )
- a. Pressurizer heaters off
- b. . Actual pressurizer level increasing due to one or_ both of ht' e following: .!
J ., 1) Letdown flow isolation.
- 2) Charging flow increasing -
- 3. The'following are possible plant responses to a failed high level transmitter:
- a. Pressurizer heaters on b'. Actual pressurizer level decreasing as charging flow decreases.
1; . B. Annunciator Responses
- 1. If a level transmitter has failed low, one or more of the following annunciators may be alarming:
;( a. Ann. A4-1B, PRESSURIZER CONTROL LEVEL HIGH/ LOW (2OM-6.4.AAK) -
" ~
- b. Ann. A4-1C, PRESSURIZER CONTROL LEVEL DEVIATION HIGH/ LOW
' (2OM-6.4. AAL)
I
- c. Ann. A4-1G,. PRESSURIZER CONTROL HEATER GROUP TROUBLE
' (2OM-6.4. AAO)
- d. Ann. A4-2G, PRESSURIZER BACKUP HEATER GROUP AUTO ON/OFF
.. _ (2OM-6.4.AAW)
- 2. If a level transmitter has failed high, one or more of the following annunciators may be alarming:
- a. Ann. A4-28, PRESSURIZER LEVEL H!GH (2OM-6.4.AAR) bl A'nn. A4-18, PRESSURIZER CONTROL LEVEL HIGH/ LOW (2OM-6.4.AAK)
- c. Ann. A4-1C, PRESSURIZER CONTROL LEVEL DEVIATION HIGH/ LOW. 1 (2OM-6.4. AAL) i
, . .L L o t
'd- .
ATT ACHMENT 1 s
Beaver Valley Power Station ' Unit 2 20M-6.4.lF Reactor Coolant System Operating Procedure issue 4 Revision 4 Page IF 10 of 40
/7 INSTRUMENT FAILURE PROCEDURE i
Q C. ! System Responses 1
- 1. A controlling channel has failed low
- a. If [2RCS*LT459] has failed low, the following occurs:
- 1) ' [2CHS*FCV122], Charging Pumps Disch Flow Control Viv, opens increasing charging flow,if in AUTO.
- 2) - [2CHS*LCV460A], Regenerative Heat Exch inlet Viv closes.
- 3) [2CHS*AOV200A,2008, and 200C], Letdown Orifices 21,23, and 22 Isols, close.
- 4) All Pressurizer Heaters are deenergized.
- b. If [2RCS*LT460] has failed low the following occurs:
- 1) [2CHS*LCV460B], Regenerative Heat Exch inlet Viv, c19 ses.
- 2) [2CHS* AOV200A, B, C], Letdown Orifices 21,23, and 22 Isols, close.
- 3) All Pressurizer Heaters are deenergized.
- c. If [2RCS*LT461] has failed low, the following occur:
- 1) If PRZR Level Control Channel Selector was in position 11 & lli,.THEN the control and alarm functions of [2RCS-LT459] occur.
- 2) If PRZR Level Control Channel Selector was in position I & 111 THEN the control and alarm function of [2RCS-LT460] occur.
- 2. A controlling channel has failed high
- a. If [2RCS*LT459] has failed high, the following occur
- 1) Ann. A4-28, PRESSURIZER LEVEL HIGH, alarms AND Pri Plant y
Parameters Status Panel 308 Status Light AS, PRZR HIGH LEVEL RX L _ TRIP CHAN I is ON. L- . 2) [2CHS*FCV122], Charging Pumps Disch Flow Control Viv, closes I reducing charging flow.
- 3) PRZR Heaters Control Groups A and D AND Backup Groups B and E are on.
- b. If [2RCS'LT460] has failed high, the following occur:
- 1) Ann. A4-28, PRESSURIZER LEVEL HIGH, alarms AND Pri Plant -
Parameters Status Panel 308 Status Light B5, PRZR HIGH LEVEL RX TRIP CHAN 11 is ON. 4 U . 1 a ATTACHMENT 1
- . _ _ .. _ _ . _ . . _ _ _ _ . _ _ -. _ _ _ _ _. _ .m m.
l l Beaver Valley Power Station Unit 2 20M-6.4.lF L Reactor Coolant System issue 4 Revision 4 f Operating Procedure Page IF 11 of 40 INSTRUMENT FAILURE PROCEDURE d
- c. If [2RCS*LT461] has failed, the following occur:
- 1) Ann. A4-28, PRESSURIZER LEVEL HIGH, alarms AND Fci Plant Parameters Status Panel 308 Status Light CS, PRZR HIGH LEVEL RX TRIP CHAN lit is ON.
- 2) Il PRZR Level Control Channel Selector was in position 11 & 111 THEN the control functions of [2RCS*LT459] occur.
- 3) If PRZR Level Control Channel Selector was in position I & lil, THEN the control functions of [2RCS*LT460] occur.
Ill. INSTRUMENT SYSTEM DESCRIPTION / FUNCTIONS A. The three pressurizer level channels provide the following indication, control and safety functions during startup and operation.
- 1. Independent signals to actuate high and low level alarms. -
- 2. Independent signal to activate high level reactor trip signals. The reactor trip requires two out of three of those signals to actuate.
- 3. Each transmitter also provides a signal for a level indicator located on BB-B. Also j
[2RCS*LT459 and 460] each provides a signal for [2RCS-Ll459C and 460A],
'g Pressurizer Level indicators, on the Emer Shutdown Panel.
J
- 4. Each transmitter also provides a signal to deenergize all pressurizer heaters on low level, i 1
- 5. Each transmitter provides a signal that will close [2CHS*AOV200A, B, and C], )
Letdown Orifices 21,23 and 22 Isols, if pressurizer level is < 14% of the level j span.
- t 6. Each transmitter supplies a signal to close one of [2CHS*LCV460A or B],
Regenerative Heat Exchanger Letdown inlet Valves, ([2RCS*LT459/461] to [2CHS*LCV460A] and selected [2RCS*LT460/461] to [2CHS*LCV460B]). 4 B. In addition to the above [2RCS*LT459 or 461] provides the following specific functions. ;
- 1. Supplies a signal to the level setpoint controller which is compared to the reference level setpoint to actuate the following:
- a. 5% below reference level activates low level deviation alarm.
- b. 5% above reference level activates high level deviation alarm and energizes PRZR Heaters Control Groups A and D AND Backup Groups B and E.
- 2. Provide a signal to [2CHS*FCV122), Charging Pumps Disch Flow Control Viv, to l control the charging rate to maintain the reference level in the pressurizer.
C. Also. [2RCS*LT460 or 461] will actuate a high level alarm when pressurizer level O exceeds 70% of the level span. t l ATTACHMENT 1
. . , , .. . - - - - . . - - _ - . - - . - . - . - - . . . - - . . ~ _ .-
Beaver Valley Power Station' Unit 2 2OM-6.4.IF Reactor Coolant System Operating Procedure issue 4 Revision 4 Page IF 12 of 40 [ INSTRUMENT FAILURE PROCEDURE f
?m]./ ,
IV. TABLES / DRAWINGS TABLE 1 J CHANNEL REFERENCE BISTABLE LOCATION FUNCTION 2RCS-L459 2MS P-6.23-1 2LS/459A-1 (BS-1) RK*2PRI-PROC-1 High Level Rx Trip CF4 Slot 42 2RCS-L460 - 2MSP-6.24-1 2LS/460A-1 (BS-1) R K*2PRI-PROC-2 High Level Rx Trip CF4 Slot 42 q 2RCS-L461 2MS P-6.25-1 2LS/461 A-1 (BS-1) RK*2PRI-PROC-3 High Level Rx Trip CF7 Slot 35 1 l l e
,\ g i-5 Ob 1 .l Q -
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T 5 E 3' o gr8 .< F Median Ref. Tavg 461 460 - 459 - g "ru" H Tavg 547' 4 S - 2f ,l n_- A k~? ex gm' e r-Z 18'EL *a C o y
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~ Beaver Valley Power Station Unit 2 20M-6.4.lF Reactor Coolant Sysicm issue 4 Revision 4 Operating Procedure Page IF 14 of 40 lf/O-
?%) INSTRUMENT FAILURE PROCEDURE V. REFERENCES' I A. TECHNICAL SPECIFICATIONS t l l l 1.: BVPS-2 T.S. 3.3.1.1 1
- 2. BVPS-2 T.S. Table 3.3-1, item 11
-l
- 3. BVPS-2 T.S. 3.3.3.5 i
- 4. BVPS-2 T.S Table 3.3-9, item 8 i
- 5. BVPS-2 T.S. 3.3.3.8
' 6, BVPS-2 T.S. Table 3.311, item 1 *
- 8. UPDATED FINAL SAFETY ANALYSIS REPORT
- 1. UFSAR-2 Section 7.2.1.1.2
- 2. UFSAR-2 Figure 7.2-1 Sheet 6
- 3. UFSAR-2 Section 7.2.2.3.4 C. COMMITMENTS NONE r
.(V/ ..
.)
i-Tm.s D. ADMINISTRATIVE
- NONE i
' E. VENDOR INFORMATION
- 1. 2001.410-001-123, Pressurizer Level Protection i I
- 2. 2001.410-001 133, Pressurizer Level Protection 11
'3. 2001.410-001-145, Pressurizer Level Protection til
- 4. 2001.409-001-022, Functional Diagram Pressurizer Trip Signals F. DR AWINGS -
1.112241-LSK-25-6D, Logic Diagram Pressurizer Control 2.- 12241-LSK-25-6E, Logic Diagram Pressurizer Control
- 3. -12241-LSK-25-6F, Logic Diagram Pressurizer Control
- 4. 12241-LSK-25-6G, Logic Diagram Pressurizer Control 7 ' 5. 1?".41-LSK-25-13A, Logic Diagram Reactor Coolant System Reactor Coolant Letdown 1 l 6. 12241-LSK-25-13B, Logic Diagram Reactor Coolan! System Reactor Coolant Letdown -
l({ l l9% 7. 12241-LSK 25-13C. Logic Diagram Reactor Coolant System Reactor Coolant l Letdown - j
- 8. -;12241-LSK-2G-1G, Logic' Diagram Charging Pumps ATTACHMENT 1
i
- Beaver Valley Fower Station ' Unit 2 20M-6.4.lF l
l- Reactor Coolant System issue 4 Revision 4 l- Operating Procedure Page IF 15 of 40 INSTRUMENT FAILURE PROCEDURE G. ' OPERATING MANUAL
- 1. 20M-6.1, Reactor Coolant Systern. Description l 2. 2OM-6.4.AAR, Pressurizer Level High
- 3. 2OM-6.4.AAK, Pressurizer Control Level High/ Low
- 4. 2OM-6.4.AAL, Pressurizer Control Level Deviation High/ Low
- 5. 20M-6.4AAO, Pressurizer Control Heater Group Trouble
- 6. - 20M-6.4.AAW, Pressurizer Backup Heater Group Auto-Close/ Trip H. - PLANT MODIFICATIONS .
NONE- -
- - ~1
- OTHER
- 1. 2MSP-6.23-1,2RCS-L459 Pressurizer Level Loop' P:0tection Channel l Test
. 2. 2MSP-6.24 l,2RCS-L460 Pressurizer Level Loop Protection Channel 11 Test L-
. 3. 2MSP-6.25-1,2RCS-L461 Pressurizer Level Loop Protection Channel til Test
'4. OMCR 2-94-2070; 2-95-0232 (Rev,2).
- 5. OMCR 2-95-0496 (Rev. 3).
- 6. OMCR 2-96-0252,0312 (Rev 4). j t.
- [_~,
l% [ 3 ATTACHMENT 1
Besver Valley Power Station Unit 2 20M-6.4.lF Reactor Coolant System issue 4 Revision 4 Operating Procedure Page IF 16 of 40 l INSTRUMENT FAILURE PROCEDURE <v ATTACHMENT 2 i I [2RCS* PT444, 445, 455, 456, 457] i
- 1. OPERATOR RESPONSESISYSTEM RESTORATION Note: Failure of any channel will require protection and engineered safety feature I system input determination and possible bistable tripping. -
A. Identify which channel has failed and how it has l'ailed by comparing [2RCS'P1444 and 445], PRZR CONTROL PRESS, on VB-B OR [2RCS*PI 455,456, and 457], PRZR Channel 1,2, and 3 Press, on 88-8. B. If [2RCS*PT444] has failed, perform the following:
- 1. If [2RCS*PT444] has failed low, perform the following:
- a. Manually control PZR Heaters Control Groups A and D AND Backup Groups B and E as necessary to control pressure.
- b. Manually control [2RCS-PCV455A and 455B], PRZR Spray Valve Control, as
.necessary to control pressure.
- c. Proceed to Step E. l
- 2. If [2RCS*PT444] has failed high, perform the following:
- a. Place the control switch for [2RCS*PCV455C], PZR PORV, to close.
, b. Place [2RCS-PK444A] PRZR Press Control in MANUAL, THEN Perform the
, following:
- 1) Take manual control of [2RCS-PCV455A and 4558), PRZR Spray Valve Control, to reduce spray flow to control RCS pressure.
- 2) Take manual control of PRZR Heater Control Groups A and D AND Sackup Groups B and E as necessary to control pressure.
~
- 3) Take manual control of PRZR Heaters Control Group C.
- c. Proceed to Step E.
C. 'If [2RCS'PT445] has failed, perform the following:
- 1. If [2RCS*PT445] has failed low, proceed to Step F.
l
- 2. If [2RCS PT445] has failed high, perform the following:
, a. Place tbe control switches for [2RCS*PCV455D and 456], PZR PORV's, to I /O close.
\)
- b. Proceed to Step E.
)
ATTACHMENT 2
' Bravar Vall:y Power Station Unit 2 2OM-6.4.lF Reactor Coolant System Issue 4 Revision 4 Operating Procedure Page IF 17 of 40 m a- INSTRUMENT FAILURE PROCEDURE (Y
D. If [2RCS*PT455,456, or 457] has failed. THEN ensure OTAT/OPAT setpoint recorder [2RCS-TR412] loop selector switch is positioned to record an operable channel AND proceed to Step E. E. Refer to the following Technical Specifications to determine the required bistables to. trip by placing them in test: Note:
' Table 1 of this Attachment lists the bistables and locations.
- Key 117 or 118 is needed to unlock the protection racks.
1 Th ~7 (.oTA:D 1
- 1. T.S. 3.3.1.1 and Table 3.3-10ltems 9 (> P-7) and 10 Reactor Trip Instrumentation, )
Applicable Modes 1 & 2
- 2. T.S. 3.3.2.1 arid Table 3.3-3 Items 1.d and 8.b (P-11), Engineered Safety Feature Actuation System Instrumentation, Applicable Modes 1,2, & 3.
- 3. T.S. 3.3.3.5 and Table 3.3-9, item 7, Remote Shutdown Instrumentation, Applicable Modes '1,2, & '3 (Applicable to [2RCS*PT444,455] only).
F. Repairs i Initiate and MWR to investigate the cause and repair the failed channel. r]d ( 1. j G. If [2RCS*PCV455C (455D)(456)] PRZR PORV has opened AND flow through the PORV ! has occured, have the STA record the PORV actuation in the " Transient Log ~t
- 1. If a PORV actuation Design Transient entry does not exist in the Transient Log, ,
have the STA write an EM to NED with the following information: '
- a. The mark number of the PORV.
- b. The peak pressurizer pressure and pressurizer vapor space temperature during the actuation.
- c. The PORV loop seal temperature prior to the actuation, obtained from the Auxiliary Building Log.
II. RESPONSES VV - l A. Plant Responses PAGE 8_OF 3 l
- 1. Redundant indications confirm a high or low failure of a pressurizer pressure channel. -
- 2. Actual pressure increasing.is a possible plant response due to a low failure of a l pressure transmitter for the following reasons:
p- a. Pressurizer heaters on O b. Spray valves modulate closed
- 3. Actual pressure decreasing is a possible plant response due to a failed high pressure transmitter for the followino reasons:
i ATTACHMENT 2
Beaver Valley Power Station Unit 2 2OM 6.4.lF Reactor Coolant System Operating Procedure issue 4 Revision 4 Page IF 18 of 40 l INSTRUMENT FAILURE PROCEDURE i
- a. Pressurizer heaters off '
- b. Spray valves modulate open
- c. PORV's open B. Annunciator Responses
- 1. If a pressure transmitter has failed low, one or rnore of the following annunciators !
may be alarming:
- a. Ann A4-1D, PRESSURIZER CONTROL PRESS HIGH/ LOW (20M-6.4.AAM) i
- b. Ann A4-1E, PRESSURIZER CONTROL PRESS DEVIATION HIGH/ LOW (20M-6.4.AAN)
- c. Ann A4-2D, PRESSURIZER PRESS HIGH/ LOW (2OM-6.4.AAT)
- 2. If a pressure transmitter has failed high, one or more of the following annunciators rnay be alarrning:
)
- a. Ann A4-10,' PRESSURIZER CONTROL PRESS HIGH/ LOW (20M-6.4.AAM)
' ~
- b. An'n A4-2D, PRESSURIZER PRESS HIGH/L'OW (20M-6.4.AAT) l
- c. Ann A4-1E, PRESSURIZER CONTROL PRESS DEVIATION HIGH/ LOW
, (2OM-6.4.AAN) ,
- d. Ann A4-2E, PRESSURIZER CONTROL PRESS HIGH PORV ACTUATION (20M-6.4.AAU)
- e. Ann. A4-1G PRESSURIZER CONTROL HEATER GROUP TROUBLE (2OM-6.4.AAO) f, Ann. A4-2G, PRESSURIZER BACKUP HEATER GROUP AUTO ON/OFF (20M-6.4. AAW)' . ._
C. System Responses A channel has failed low 1.
- a. If [2RCS*PT444] has failed low, the following occur:
- 1) PRZR Heaters Control Groups A and D AND Backup Groups B and E are on.
- 2) PRZR Heaters Control Group C modulates high
~
- 3) [2RCS*PCV455A and 455B] modulate closed
- b. If [2RCS*PT445] has failed low, the following occurs:
- 1) Ann A4-1D, PRESSURIZER CONTROL PRESS HIGH/ LOW, alarms.
O CEN 2-9
- PAGE_ L OF ) -
l ATTACHMENT 2
- Beaver Valley Power Station Unit 2 20M-6.4.lF l Reactor Coolant System issue 4 Revision 4 I
Operating Procedure Page IF 19 of 40
,x
( INSTRUMENT FAILURE PROCEDURE i
\ )
l c. If [2RCS* PT455 (456) (457)] has failed low the following occurs: l 1) Low pressure reactor trip signal (requires 2/3 for trip), Pri Plant Parameters Status Panel 308 Status Light A7 (87) (C7), PRZR LOW l PRESS RX TRIP CHAN I (ll) (Ill), is ON.
- 2) Safety injection signal (requires 2/3), Pri Plant Parameters Status Panel l 308 Status Light A1 (B1) (C1), PRZR PRESS LOW SI SET POINT CHAN I l (11) (111), is ON.
- 3) If pressure > 2000 psig, Pri Plant Parameters Status Panel 308 Status Light A3 (63) (C3), PRZR Si BLOCK PERM CHAN I (ll) (Ill), is ON.
l 4) If pressure > 2185 psig. Pri Plant Parameters Status Panel 308 Status Light' A2 (B2), (C2), PRZR LOW PRESS PORV BLOCK INTLK CHAN I (11) (Ill), is ON
- 2. A channel has failed high
- a. If [2RCS*PT444] has failed high, the following occurs:
- 1) [2RCS*PCV455A and 455B], Spray Valves, modulate open
- 2) [2RCS*PCV455C], PORV, opens i
( 3) All Pressurizer Heaters are off
- 4) Ann A4-1E, PRESSURIZER CONTROL PRESS DEVIATION HIGH/ LOW, may alarm l b. If [2RCS*PT445] has failed high, the following occurs:
- 1) [2RCS*PCV455D and 456], PORV's, open
- 2) Ann A4-1D, PRESSURIZER CONTROL PRESSURE HIGH/ LOW, alarms
- 3) Ann A4-2E, PRESSURIZER CONTROL PRESS HIGH PORV ACTUATION, alarms l- c. If [2RCS* PT455 (456) (457)] has failed high, the following occurs:
- 1) High pressure reactor trip signal (requires 2/3 for trip), Pri Plant Parameters Status Panel 308 Status Light A4 (84) (C4), PRZR HIGH PRESSURE RX TRIP CHAN l (ll) (Ill), is ON.
- 2) If pressure < 2000 psig, Pri Plant Parameters Status Panel 308 Status l Light A3 (B3) (C3), PRZR St BLOCK PERM CHAN I (11) (Ill), is OFF i 3) If pressure < 2185 psig, Pri Plant Parameters Status Panel 308 Status
- Light A2 (B2) (C2), PRZR LCW PRESS PORV BLOCK INTLK CHAN I (II)
(lli), is OFF r ! A k NY I 1 l ATTACHMENT 2 l
I Beaver Valley Power Station Unit 2 2OM-6.4.lF Reactor Coolant System Issue 4 Revision 4 Operating Procedure Page IF 20 of 40
.[ INSTRUMENT FAILURE PROCEDURE .'
lit. INSTRUMENT SYSTEM DESCRIPTION / FUNCTIONS A. The five pressurizer pressure channels provide the following indication, control, and safety functions during startup and operation. 1, [2RCS*PT455,456 and 457] each provides a signal to the following:
- a. Safety Injection coincidence circuitry (requires 2/3 signals to activate) ,
- b. High and low pressure trip signals to the reactor trip coincidence circuitry (requires 2/3 signals to activate).
- c. Signal to a pressure indication located on BB-B. Also [2RCS*PT455] provides a signal to [2RCS-Pl455A], PRZR C'iannel 1 Press Indicator, located on the !
' Emer Shutdown Panel.
- d. Signal to overtemperature AT protection circuits
- e. Unblock safety injection signals in P-11. RCS pressure > 2000 psig (2/3).
- f. Interlock signals to PORV's, RCS pressure > 2185 (2/3)
- 2. [2RCS*PT444] provides the following signals:
- a. Control signal to [2RCS*PCV455A and 4558]. PRZR Spray Valve Control
'U f) b. Control signal to [2RCS*PCV455C), PZR PORV )
- c. Control signal to the pressurizer heaters
- d. Signal to [2RCS-Pl444], PRZR Control Press, and [2RCS*PR444] (red pen)
Pressurizer Pressure Recorder, on VB-B
- e. Signal to [2RCS-P1444A], PRZR Channel Control Press Indicator, on the Emer
' Shutdown Panel.
- f. Signals to the pressurizer high and low pressure deviation alarms
- 3. [2RCS*PT445] provides the following signals:
- a. Control signal to [2RCS'PCV45SD and 456], PZR PORV's b.' Low pressure alarm signal .
[ c. High pressure alarm signal ! d. Signal to [2RCS*Pl445], PRZR Control Press, and [2RCS*PR445] (green pen) Pressurizer Pressure Recorder, on VB-B l l 4- i 1 t
- k) I !
4 ATTACHMENT 2
Beaver Valley Power Station Unit 2 2OM-6.4.!F Reactor Coolant System issue 4 Revision 4 Operating Procedure Page IF 21 of 40 O INSTRUMENT FAILURE PROCEDURE IV. TABLES / DRAWINGS TABLE 1 Channel Reference Bistable Location Function 2RCS-P455 2MS P-6.12-1 2PS/455A(BS-1) High Press Rx Trip RK 2PRl* Unblock Si signal 2PS/455B(BS-2) PROC-1 2PS/455C(BS-4) CF-4 Slot 28 Low Press Rx Trip 2PS/455D(BS-3) Low Press SI signal 2TS/412C-1(BS-3) RK'2PRI- Overtemp AT Rx Trip
" Overtemp AT Rod Stop 2TS/412C-2(BS-4) F M 2PS/455G(BS-1) RK*2PRI- PORV Block PROC-1 CF-4 Slot 44 2RCS-P456 2MS P-6.13 2PS/456A(BS-1) High Press Rx Trip c.. RK*2PRl" Unblock SI signal 2PS/456B(BS-2)
( PROC-2
\ 2PS/456C(BS-4) CF-4 Slot 28 Low Press Rx Trip 2PS/456D(BS-3) Low Press Si signal 2TS/422C-1(BS-3) RK'2PRi- Overtemp AT Rx Trip PRO 2 Overtemp AT Rod Stop 4
2TS/422C-2(BS-4) CF_ g 2PS/456G(BS-1) RK'2PRI- PORV Block PROC-2 CF-4 Slot 46 2RCS-P457 2MS P-6.14-1 2PS1457A(BS-1) High Press Rx Trip RK'2PRI- Unblock Si signal 2PS/457B(BS-2) PROC-3 2PS/457C(BS-4) CF-7 Slot 28 Low Press Rx Trip 2PS/457D(BS-3) Low Press Si signal 2TS/432C-1(BS-3) RK'2PRI- Overtemp AT Rx PR 3 2TS/432C-2(BS-4) p_ Overtemp AT Rod Stop 2PS/457G(BS-1) RK'2PRI- PORV Block PROC-3 CF-7 Slot 69
.f f ATTACHMENT 7
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. .- . . , - .~ .- .. - _ . . -- . . - .. . . - . . . . . _ - . . -
~ Beaver. Valley Power Station Unit 2 20M-6.4.lF
-Rcactor Coolant System issue 4 Revision 4 Operating Procedure'_ Page IF 25 of 40 y
i : INSTRUMENT FAILURE PROCEDURE
- (
V. REFERENCES'
' A. Technical Specifications ,
- 1. BVPS-2 T.S. 3.3.1.1 i
- 2. BVPS-2 Table 3.3-1, items 9 and 10
- 3. BVPS-2 T.S. 3.3.2.1 i
- 4. BVPS-2 Table 3.3-3, items 1.d and 8.b
- 5. BVPS-2 T.S. 3.3.3.5
- 6. ' BVPS-2 Table 3.3.0, item 7 i B. UPDATED FINAL SAFETY ANALYSIS REPORT
- 1. UFSAR-2 Section 7.2.1.1.3 .
- 2. UFSAR-2 Section 7.2.1.1.7
- 3. UFSAR-2 Section 7.2.2.3.3 i l
C. COMMITMENTS (b l ,V. i 'D. ' ADMINISTRATIVE l1 NONE j E. VENDOR INFORMATION j l 1. 2001.410-001-117, Pressurizer Press Protection I
, 2. '2001.410-001-127, Pressurizer Prest Protection il
- 3. 2001.410-001-139, Pressurizer Press Protection ill l
! 4. 2001.410-001-217, Pressurizer Pressure Control I l F. DRAWINGS
- 1. 12241-LSK-25-6A, Logic Diagram Pressurizer Control l'
l1 2. 12241-LSK-25-68, Logic Diagrarn Pressurizer Control
- 3. 12241 LSK-25-6C, Logic Diagram Pressurizer Control f
- j. 4. 12241-LSK-25-6F, Logic Diagram Pressurizer Control
! 5.' 12241 LSK-25-6G, Logic Diagram Pressurizer Control , t
'p r\
i i ATT ACHMENT 2
. . _ . . _ . . . ._ . _ ._ .. . _. _._ _ .. ._= ,_ _-m._.__. . m.
i
' Beaver Valley Power Station Unit 2 20M-6.4.lF !
. Reactor Coolant Systern Issise 4 Revision 4' Operating Procedure - Page IF 26 of 40
[ T .' INSTRUMENT FAILURE PROCEDURE I QF g G. OPERATING MANUAL
- 1. 2OM-6.1, Reactor Coolant System, Description
- 2. ' 2OM-6.4.AAT, Pressurizer Press High
- 3. 2OM-6.4.AAM, Pressurizer Control Press High/ Low i
- 4. ~2OM-6.4.AAN, Pressurizer Control Press Deviation High/ Low
- 5. 2OM-6.4.AAU, Pressurizer Control Press High Pwr Rif Act
- 6. 2OM-6.4.AAO, Pressurizer Control Heater Group Trouble
- 7. 2OM-6.4.AAW, Pressurizer Press Backup Heater Group Auto-Close/ Trip H. PLANT MODIFICATIONS NONE
- l. OTHER q
- 1. 2MSP-6.12-1,2RCS*P455 Pressurizer Pressure Loop Protection Channel 1 Test
- 2. 2MSP-6.13-1,2RCS*P456 Pressurizer Pressure Loop Protection Channel 11 Test
- 3. 2MSP-6.14-1,2RCS*P457 Pressurizer Pressure Loop Protection Channel 111 Test
[.N ) G. 4. OMDR 2-94-0944 (Rev.1). '-
- 5. OMCR 2-94-2070; 2-95-0069, 0232 (Rev. 2).
<. 6. OMDR 2-92-1148; OMCR 2-95-0496 (Rev. 3).
' 7. OMCR 2-96-0117 (Rev. 4). .
l;l - O ) ATTACHMENT ~2
Beaver Valley Power Station Unit 2 20M-6.4.lF Reactor Coolant System issue 4 Revision 4 Operating Procedure Page IF 27 of 40 INSTRUMENT FAILURE PROCEDURE [G ATTACHMENT 3 [2RCS* FT414, 415, 416, 424, 425, 426, 434, 435, 436]
- 1. OPERATOR RESPONSES / SYSTEM RESTORATION Note:
- Failure of any channel will require protection system input determination and possible bistable tripping.
- A failed high transmitter will not send a trip signal.
A.' identify which channel has failed by comparing [2RCS*Fl414,415,416 (424,425,426) (434, 435, 436)], RCL A (B) (C) Flow, on VB-A. B. Refer to the following Technical Specification to trip any required bistables by placing them to test: ) m Note:
+ Table 1 of this Attachment lists the bistables and location.
- Key 117 or 118 is needed to unlock the protection racks.
- 1. T.S. 3.3.1.1 and Table 3.3-1, items 12 and 13. Reactor Trip Instrumentation, Applicable Mode 1.
C. F3epairs I
- 1. Initiate an MWR to investigate the cause and repair the failed channel.
ll RESPONSES A. Plant Responses l
- 1. Redundant indications confirm failure of a loop flow transmitter ,
l
- 2. A failed low flow transmitter will send one signal to a two of three coincidence circuit for a reactor trip.
I B. A'nnunciator Responses Note: A failed high transmitter will NOT cause any annunciators to alarm. . .' 1. If a flow transmitter has failed low, one of the following annunciators may be l Cd .: alarming:
- a. Ann A2-SE, REACTOR COOLANT LOOP FLOW LOW (20M-6.4.AAF)
I ATT ACNMENT 3 1
_. . . - -- . - . - - . . - _ . - - - . - _ _ - . - - - - . . - -.-_~. . Beaver Valley Power Station Unit 2 20M-6.4.lF Reactor Coolant System issue 4 Revision 4 Operating Procedure Page IF 28 of 40 V) INSTRUMENT FAILURE PROCEDURE C. System Responses
- 1. If one channel of [2RCS*FT414,415, or 416] has failed low, the following occurs;
- a. Ann A2-SE, REACTOR COOLANT LOOP FLOW LOW, alarms.
- b. One trip signal is sent to a two out of three reactor trip circuit. (requires two signals from [2RCS FT414,415 or 416] to trip)
- c. Reactor Coolant Pumps Status Panel 465 Status Li0 ht A3, B3, or C3, RCS LOOP A FLOW LOW CHAN I,11, or lil, is ON
- 2. If one channel of [2RCS*FT424,425, or 426] has failed low, the following occurs;
- a. Ann A2-5E, REACTOR COOLANT LOOP FLOW LOW, alarms.
- b. One trip signal is sent to a two out of three reactor trip circuit. (requires two signals from [2RCS*FT424,425, or 426] to irip)
- c. Reactor Coolant Pumps Statu:, Panel 465 Status Light A4,84, or C4, RCS LOOP B FLOW LOW CHAN I,11, or lit, is ON
- 3. If one channel of [2RCS*FT434,435, or 436] has failed low the following occurs: l
- a. Ann A3-120) REACTOR COOLANT LOOP FLOW LOW, alarms,
\
- b. One trip signal is sent to a two out of three reactor trip circuit. (requires two signals from [2RCS*FT434,435, or 436] to trip)
) l
- c. Reactor Coolant Pumps Status Panel 465 Status Light AS,85, or CS, RCS LOOP C LOW FLOW CHAN I,11, OR 111, is ON lli. INSTRUMENT SYSTEM DESCRIPTION /FUCTIONS A. Each loop of the reactor coolant system has three flow transmitters and a 2/3 coincidence circuit sends a signal to one of two circuits for a reactor trip. At > P-7 it requires trip signals from two loops, while at > P-8 only one loop trip signal is needed for a reactor trip.
B. Each flow transmitter also supplies a signal to flow indication located on VB-A. p l s ! ATTACHMENT 3 !~ _ _ .
Beaver Valley Power Station - Unit 2 2OM-6.4.lF Reactor. Coolant Systern issue 4 Revision 4 Operating Procedure Page IF 29 of 40
- o.
1 I' INSTRUMENT FAILURE PROCEDURE LJ IV. TABLESI. DRAWINGS TABLE 1 Channel Reference Bistable Location Function 2RCS-F414 2MS P-6.03-1 2FS/414A(BS-1) RK'2PRI Low Flow Alarm & Rx Trip Signal Loop 1 A PROC-1 - CF-4 Slot 32 2RCS-F415 2MSP-6.06-1 2FS/415A(BS-1) RK*2PRI Low Flow Alarm & Rx Trip Signal Loop 1 A PROC-2 CF-4 Slot 32 2RCS-F416 2MS P-6.09-1 2FS/416A(BS-1) RK'2PRI Low Flow Alarm & Rx Tr,ip Signal Loop 1 A PROC-3 CF-7 Slot 32 2RCS-F424 2MS P-6.04-1 2FS/424A(BS-1) RK'2PRI Low Flow Alarm & Rx Trip Signal Loop 1B PROC-1 CF-4 Slot 33 Low Flow Alarm & Rx Trip Signal Loop 18 - A) ( Ad 2RCS-F425 2MS P-6.07-l 2FS/425A(BS-1) RK*2PRI PROC-2 CF-4 Slot 33 2RCS-F426 2MS P-6.10-1 2FS/426A(B3-1) RK*2PRI Low Flow Alarm & Rx Trip Signal Loop 18 PROC-3 CF 7 Slot 33 2RCS-F434 2MSP-6.05-1 2FS/434A(BS-1) RK*2PRI Low Flow Alarm & Rx Trip Signal Loop 1C
'. PROC-1 CF-4 Slot 34 2RCS-F435 2M S P-6.08-1 2FS/435A(BS-1) RK'2PRI Low Flow Alarm & Rx Trip Signal Loop 1C
' PROC-2 CF-4 Slot 34 2RCS-F436 2MSP-6.11-1 2FS/436A(BS 1) RK 2PRI Low Flow Alarm & Rx Trip Signal Loop 1C PROC-3 CF-7 Slot 34
'{ . ATTACHMENT 3
l: Beaver Valley Power Station Unit 2
=
2OM-6.4.lF i: Reactor Coolant System issue 4 Revision 4
. Operating Procedure Page IF. 30 of 40 ff s)I . INSTRUMENT FAILURE PROCEDURE )
i L V. . REFERENCES . i l . A. Technical Specifications 1 { l 1. BVPS-2 3.3.1.1 2.- . BVPS-2 Table 3M-1, items 12 and 13 l , B. UPDATED FINAL SAFETY ANALYSIS REPORT
- 1. UFSAR-2 Section 7.2.1.1.4 C. COMMITMENTS NONE D. ADMINISTRATIVE NONE E. VENDOR INFORM ATION '
- 1. 2001.409-001-021, Functional Diagrams Primary Coolant System Trip Signals
- 2. 2001.410-001-120. Loop 1,2 Reactor Coolant Flow Protection 1
- 3. 2001.410-001-121, Loop 3 Reactor Coolant Flow Protection 1
.(% )
- 4. 2001.410-001-130, Loop 1,2 Reactor Coolant Flow' Protection 11 -
- 5. 2001.410-001-131, Loop 3 Reactor Coolant Flow Protection il
- 6. 2001.4104101-143, Loop 1,2 Reactor Coolant Flow Protection lli :
7, 2001.410-001-144, Loop 3 Reactor Coolant Flow Protection 111 F: DRAWINGS NONE G. OPERATING MANUAL
- 1. 2OM-6.1, Reactor Coolant System Description
- 2. 2OM-6.4.AAF, Reactor Coolant Loop Flow Low
. H. PLANT MODIFICATIONS NONE
, /~(N) .
)
l l:' ATTACHMENT 3
Beaver Valley Power Station Unit 2 20M-6.4.l F Reactor Coolant System issue 4 Revision.4 Operating Procedure Page IF 31 of 40 INSTRUMENT FAILURE PROCEDURE I .' OTHER
- 1. 2MSP-6.03-1,2RCS-F414 Reactor Coolant Flow Loop 1 Channel l Test
- 2. 2MSP-6.04-1,2RCS-F424 Reactor Coolant Flow Loop 2 Channel i Test
- 3. 2MSP-6.05-1,2RCS-F434 Reactor Coolant Flow Loop 3 Channel i Test
- 4. 2MSP-6.06-1,2RCS-F415 Reactor Coolant Flow Loop 1 Channel 11 Test
- 5. 2MSP-6.07-I,2RCS-F425 Reactor Coolant Flow Loop 2 Channel 11 Test
- 6. 2MSP-6.08-l,2RCS-F435 Reactor Coolant Flow Loop 3 Channel 11 Test
- 7. 2MSP-6.09-1,2RCS-F416 Reactor Coolant Flow Loop 1 Chanr.el I!.! Test
- 8. 2MSP-6.10-1,2RCS-F426 Reactor Coolant Flow Loop 2 Channel lil Test
- 9. 2MSP-6.11-1,2RCS-F436 Reactor Coolant Flow Loop 3 Channel ill Test
- 10. OMCR 2-94-2070; 2-95-0232 (Rev. 2).
A. V. ATTACHMENT 3
Beaver Valley Power Station Unit 2. 20M-6.4.lF Reactor Coolant System issue 4 Revision 4 Operating Procedure. Page IF 32 of 40 INSTRUMENT FAILURE PROCEDURE N ATTACHMENT 4 [2RCS*TE412B1, B2, 83, D (422B1, B2, 83, D) (432B1, B2, 83, D)]
- 1. OPERATOR RESPONSES / SYSTEM RESTORATION Note:
- Control responses will NOT occur if a single channel fails.
- Failure of any channel will require protection system input determination and possible bistable tripping.
A. Identify which temperature channel has failed and how it has failed by comparing the following indications:
- 1. [2RCS-Tl412D], LOOP 1 PROT T AVG (VB-B) j
- 2. '[2RCS-Tl422D], LOOP 2 PROT T AVG (VB-B)
- 3. [2RCS-Tl432D], LOOP 3 PROT T AVG (VB-B) 73 3 4
) 4. [2RCS'Tl412A] LOOP 1 PROT AT (VB-B) /
- 5. [2RCS'Tl422A] LOOP 2 PROT AT (VB-B) .
I
- 6. [2RCS*T1432A] LOOP 3 PROT AT (VB-B)
B. To determine if loop Tn RTD failed, compare the following computer points:
- 1. For Reactor Coolant Loop A, compare the following:
- a. [T0401 A], RCL A NR THOT 12RCS*TE41281
- b. [T0402A], RCL A NR THOT 2 2RCS'TE41282
- c. [T0404A], RCL A NR THOT 3 2RCS*TE41283 i I
- 2. For Reactor Coolant Loop B, compare the following:
- a. [T0421 A], RCL B NR THOT 12RCS'TE422B1 l
- b. [T0422A], RCL B NR THOT 2 2RCS*TE422B2
- c. [T0424A], RCL B NR THOT 3 2RCS*TE42283
- 3. For Reactor Coolant Loop C, compare the following:
- a. [10441 A], RCL C NR THOT 12RCS*TE432B1
! b. [T0442A], RCL C NR THOT 2 2RCS*TE43282 l
- c. [T0444A], RCL C NR THOT 3 2RCS*TE43283 )
C. To determine if Tc RTD has failed, compare the following computer points: l 1. [T0405A], RCL A NR TCOLD 2RCS*TE412C/D L ATT ACHMENT 4
, 'Bzaver Valley Power Station Unit 2 20M-6.4.lF l Reactor. Coolant System issue 4 Revision 4 Operating Procedure Page IF 33 of 40 j r.p l* I - INSTRUMENT FAILURE PROCEDURE i LV
- 2. [T0425A], RCL 8 NR TCOLD 2RCS*TE422C/D
- 3. [T0445A], RCL C NR TCOLD 2RCS*TE432C/D D. Select an unaffected channel for the OTAT and OPAT Setpoint recorder by placing the OTAT/OPAT Set Point Recorder Loop Selector switch on BB-B to an unaffected loop position.
E. Refer to the following Technical Specifications to trip any required bistables by placing them in test.
. Note:
- Table 1 of this Attachment lists the bistables and locations.
- Key 117 or 118 is needed to unlock the protection racks.
- 1. T.S. 3.3.1.1 and Table 3.3-1, items 7 and 8. Reactor Trip Instrumentation, Applicable Modes 1 & 2.
F. Repairs
. 1. Initiate an MWR to investigate the cause and repair the failed channel, i -- (.) II. RESPONSES A. Plant Response
- 1. Redundant indications confirm a high or low failure of a loop temperature channel.
- 2. Failure of a single loop temperature channel, high or low, will not cause any
. control responses.
B. Annunciator Responses
- 1. If a loop Tgtemperature channel has failed high, one or more of the following annunciators may be alarming:
- a. Ann. A4-3F, LOOP T,vc DEVIATION (2OM-1.4.AAT)
- b. Ann A4-4C, LOOP AT DEVIATION (20M-1.4.AAU)
- c. Ann. A4-3C, TAvc DEVIATION FROM Tagg (2OM-1.4.AAV)
- d. Ann. A4 3A, LOOP OVERPOWER AT (20M-1.4.AAW)
- e. Ann. A4-4A, LOOP OVERPOWER AT AUTO-TURB RNBK BLOCK ROD W/D
' (2OM 1.4.AAX)
- f. Ann. A4-4D, LOOP T,va HIGH (20M-1.4.AAY)
A-
- g. Ann. A4-3B, LOOP OVERTEMPER ATURE AT (2OM-1.4.AAZ)
'1
- h. Ann. A4-48, LOOP OVERTEMP AT AUTO TURB RNBK BLOCK POD W/D (20M 1.4.ABA)
ATTACHMENT 4
~
Beaver Valley Power Station Unit 2 20M-6.4.lF Reactor Coolant System issue 4 Revision 4 Operating Procedure Page IF 34 of 40 l [3 -INSTRUMENT FAILURE PROCEDURE \ N /-
- 2. .lf a loop Tc temperature channel has failed high, the following annunciators may be alarming:
- a. Ann. A4-3F, LOOP Tive DEVI ATION (2OM-1.4.AAT) .
- b. Ann. A4-4C, LOOP AT DEVIATION (20M-1.4.AAU)
= c. Ann. A4-3C, Tiva DEVIATION FROM Tacg (20M-1.4.AAV)
- d. Ann. A4-38, LOOP OVERTEMP AT (2OM-1.4.AAZ)
- 3. If a loop Tutemperature channel has failed low, the following annunciators may be alarming: -l
- a. Ann. A4-3F, LOOP T,vc DEVI ATION (2OM-1.4.AAT)
- b. Ann. A4-4C, LOOP AT DEVI ATION (2OM-1.4.AAU)
- c. Ann. A4-3C, T,vc DEVI ATION FROM Tgg, (2OM-1.4.AAV)
- 4. If a loop Tc temperatures channel has failed low, the following annunciators may be alarming:
- a. Ann. 'A4-3F, LOOP Tive DEVIATION (2OM-1.4.AAT)'
- b. Ann. A4-4C, LOOP AT DEVIATION (20M-1.4.AAU) -
- c. Ann. A4-3C, T,vc DEVIATION FROM Tag, (20M-1.4.AAV) ~
- d. Ann. A4-3A, LOOP OVERPOWER AT (2OM-1.4.AAW)
- e. Ann. A4-4A, LOOP OVERPOWER AT AUTO TURB RNBK BLOCK ROD W/D _ -l (2OM-1.4.AAX) l l
- f. Ann. A4-3B, LOOP OVERTEMPERATURE AT (20M-1.4.AAZ)
'. - g. Ann. A4-48, LOOP OVERTEMP AT AUTO-TURB RNBK BLOCK ROD W/D (2OM-1.4. AB A)
C. System Response
- 1. Failure of single loop temperature channel will not cause any control responses.
- 2. If [2RCS*TE412 B1, B2, B3 (422 B1, B2, B3) (432 B1, B2 B3)] fails high, the following occur:
- a. Ann. A4-3F, LOOP T,yc DEVI ATION, alarms
- b. ~ Ann. A4-4C, LOOP AT DEVI ATION, alarms
- c. Ann. A4-3C, T,vc DEVIATION FROM Taty, alarms
- d. Ann. A4-3A, LOOP OVERPOWER AT, alarms l: e. A'nn. A4-4A, LOOP OVERPOWER AT AUTO-TURB RNBK BLOCK ROD W/D. I
!. alarms
- f. Ann. A4-4D, LOOP T,vc HIGH, alarms
- g. Ann. A4-38, LOOP OVERTEMPER ATURE AT, alarms A TTACHMENT .I j
Beaver Valley Power Station Unit 2 20M 6.4.lF Reactor Coolant System issue 4 Revision 4 i Operating Procedure Page IF 35 of 40 f- ' INSTRUMENT FAILURE PROCEDURE r( ,
- h. Ann. A4-48, LOOP OVERTEMP AT AUTO-TURB RNBK BLOCK ROD W/D, alarms
. i. One si0nalis sent to the two out of three matrix for the following:
- 1) Loop overpower AT reactor trip, Pri Plant Parameters Status Panel 308 Status Light A21 (B21) (C21), RCS Loop A (B) (C) OP AT Rx Trip, is ON
- 2) Loop overpower AT auto turbine runback and rod withdrawa!
- rip, Pri Plant Parameters Status Panel 308 Status Light A19 (B19) p. 'CS Loop A (B) (C) OP AT Runback, is ON l
- 3) Loop overtemperature AT reactor trip, Pri Plant Parameters Status Panel l
30d Status Light A20 (B20) (C20), RCS Loop A (B) (C) OT AT Rx Trip, is ON
- 4) Loop overtemperature AT auto turbine runback and rod withdrawal block trip, Pri Plant Parameters Status Panel 308 Status Light A18 (B18) (C18),
RCS Loop A (B) (C) OT AT Runback, is ON
- 3. If [2RCS'TE41281, B2, B3 (422B1, B2, B3)(43281, B2, B3)] fails low, the following occur:
. a. Ann. A4-3F, LOOP T,vc DEVIATION, alarms 4
)- b. Ann. A4-4C, LOOP AT DEVI ATION, alarms t
- c. Ann. A4-3C, T,vc DEVIATION FROM Tagg, alarms
- 4. If [2RCS*TE412D(422D)(432D)] fails high, the following occurs:
- a. Ann. A4-3F, LOOP Tavo DEVIATION, alarms
- b. Ann. A4-4C, LOOP AT DEVIATION, alarms
- c. Ann. A4-3C, T,vc DEVIATION FROM Tatr, alarms
- d. Ann. A4-4D, LOOP Tavo HIGH, alarms
- 5. If [2RCS'TE412D(422D)(432D)] fails low, the following occurs:
- a. Ann. A4-3F, LOOP T,vc DEVIATION, alarms
- b. Ann. A4-4C, LOOP AT DEVIATION, alarms
- c. Ann. A4-3C, T Avc DEVIATION FROM Tagg, alarms
- d. Ann. A4-3A, LOOP OVERPOWER AT, alarms
- e. Ann. A4-1A, LOOP OVERPOWER AT AUTO-TURB RNBK BLOCK ROD W/D, alarms
- f. Ann. A4-30, LOOP OVERTEMPERATURE AT, alarms O g. Ann. A4-48, LOOP OVERTEMP AT AUTO-TURB RNBK BLOCK ROD W/D,
.- alarms ATTACHMENT 4
.. ..m _
l Beaver Valley Powcr Station Unit 2 20M-6.4.lF l Reactor Coolant System - Issue 4 Revision '4 l lL , Operating Procedure Page IF 36 of 40 I ob O Q.) INSTRUMENT FAILURE PROCEDURE i l- til. INSTRUMENT SYSTEM DESCRIPTION / FUNCTIONS
' A. Each loop temperature channel provides the following indications during startup and )
operation
- 1. Loop hot leg temperature. This is an averaged value from three RTD's located in the hot leg. .
- 2. Loop cold leg temperature. This indication is from a single RTD. An installed spare is available. !
^
B. The hot leg temperature and the cold leg temperature are used to develop the following:
- 1. . T,vc - Average loop temperature providing the following indication, control, and safety functions: !
- a. High T,vc alarm'- .
- b. T,vc Deviation from Tm alarm
- c. Low T,vc alarm. Each loop also provides one signal to a two of three matrix to close fesdwater valves off this bistable. ;
, d. Loop T,vc Low-Low alarm. Each loop also provides one' signal to a two of I three matrix to close steam dump valves off this bistable. ,/
(' ~!
- e. Each loop provides a T,vc signal to a signal selector which determines the median T,ve. This signal is compared to each loop T,vc to provide the Loop T,vc Deviation alarm. The median signal is also used by the rod control system.
- f. T,vc signals are also sent to the following indications in the control room:
- 1) [2RCS-Tl412D]. LOOP 1 PROT T AVG (VB-B) -l
- 2) [2RCS-Tl422D], LOOP,2 PROT T AVG (VB-B)
- 3) [2RCS-Tl432D]. LOOP 3 PROT T AVG (VB-8)
~
- 4) [2RCS-TR408], MEDIAN T AVERAGE TEMP. REFERENCE (VB-B)
- 2. Delta-T (AT) - Temperature difference between the hot leg average temperature and the cold leg temperature provides the following indication, control, and safety functions. ,
- a. Loop Overpower Delta-T alarm. Each loop also provides one signal to a two of three matrix for a reactor trip off this bistable.
- b. Loop Overpower Delta-T Auto Turbine Runback and Block Rod Withdrawal i alarm. Each loop also provides one . signal to a twn of three matrix to block
. rod withdrawal and start turbine runback off this bistable.
I\ ; ' c. Each loop provides a AT signal to a signal selector which determines the 1 median AT. This signal is compared to each loop AT to provide the Loop
' Oelta-T Deviation alarm. This median signalis also sent to the rod control i system.
ATTACHMENT 4
Beaver Valley Power Station Unit 2 20M-6.4.lF Reactor Coolant System issue 4 Revision 4 Operating Procedure Page IF 37 of 40 INSTRUMENT FAILURE PROCEDURE v
- d. AT signals are also sent to the following indicators in the control room: ,
- 1) [2RCS-Tl412A] LOOP 1 PROT AT (VB-8)
- 2) [2RCS-Tl422A], LOOP 2 PROT AT (VB-B)
- 3) [2RCS-T1432A], LOOP 3 PROT AT (VB-8)
- 4) [2RCS-TR412], DELTA T. OVERTEMP SP, OVERPOWER SP (VB-B) ,
- 5) [2RCS-Tl412C (422C) (432C)], Loop 1 (2) (3) OTAT Setpoint (BB-B)
- 6) [2RCS-T14128 (4228) (432B)], Loop 1 (2) (3) OPAT Setpoint (BB-B)
- 3. In addition T,vo signal is also sent to a summator where it is combined with upper and lower level reactor flux signals and pressurize pressure signal. The resulting signalis sent to a comparator where it is compared to the loop AT signal. The- ,
final output signalis sent to the followin'g : ' v a. Loop Overtemperature Delta-T alarm. Each loop also provides one signal to a
' two of three matrix for a reactor trip off this bistable.
- b. Loop Overtemperature Delta-T Auto Turbine Runback and Block Rod Withdrawal alarm. Each loop also provides one signal to a two of three ,
matrix to block rod withdrawal and start turbine runback off this bistable. l gg
- 4. In addition the average hot leg temperature and cold leg temperature can be obtained at the Shutdown Panel.
i 1 1
-[
ATTACHMENT 4
Beaver Valley Power Station Unit 2- 20M-6.4,lF Reactor Coolant System issue 4 Revision 4' Operating Procedure Page IF 38 of 40 (q INSTRUMENT FAILURE PROCEDURE g : IV. TABLESIDR AWINGS TABt E 1 Channel Reference Bistable Location Function
. 2RCS'TE 2 MS P-6.20-1 2RCS TS/412B-1 Protection Overpower AT Rx Trip 412D,B1,82,B3 (BS-1) Rack No. C1 CF4-Slot 21 I* I 2RCS-TS/412B-2 Overpower AT Turb Rnbk & Block Rod (BS-2) W/D 2RCS-TS/412C-1 Overtemp AT Rx Trip (BS-3)
LOOP 1 2RCS-TS/412C-2 Overtemp AT Turb Rnbk & Block Rod (BS-4) W/D 2RCS-TS/4120-1 Protection Low Tavg Close Feedwater Valves (BS-2) Rack No. C1 . F4-Slot 22 Low-Low Tavg, Close Steam Dump 2RCS-TS/412E (BS-1) Valves ] 2RCS'TE - 2M SP-6.21-1 2RCS-TS/42281 Protection Overpower AT Rx Trip l 422 D,81,82,B3 (BS-1) Rack No. C2 (N42) CF4-Slot 21 Overpower AT Turb Rnbk & Block Rod 2RCS-TS/GB4 O (BS-2) W/D 2RCS-TS/422C 1 Overtemp AT Rx Trip , (BS-3) l LOOP 2 2RCS-TS/422C.2 Overtemp AT Turb Rnbk & Block Rod (BS-4) W/D j 2RCS-TS/422D 1 Protection Low Tavg. Close Feedwater Valves (BS-2) Rack No. C2 CF4-Slot 22 Low-Low Tavg, Close Steam Dump 2RCS-TS/422E (BS-1) Valves 2RCS'TE 2MSP-6.22-1 2RCS-TS/43281 ~ Protection Overpower AT Rx Trip 432D,B1,82,83 (BS-1) Rack No. C3 (N43) Si t 21 Overpower AT Turb Rnbk & Block Rod 2RCS-TS/4328-2 (BS-2) W/D 2RCS-TS/432C 1 Overtemp AT Rx Trip (BS-3) 1 I LOOP 3 2RCS-TS/432C-2 Overtemp AT Turb Rnbk & Block Rod (BS-4) W/D 2RCS-TS/432D-1 Protection Low Tavg. Close Feedwater Valves (BS 2) Rack No. C3 Si t22 Low-Low Tavg, Close Steam Dump 2RCS-TS/432E (BS-1) Valves Note: 2RCS-TS/412D-2 (4220 2) (432-D2) Bistable Hi Tavg Alarm need not be tripped. U(h , I ATTACHMENT 4 1
Beaver Valley Power Station Unit 2 - 20M-6.4.lF-Reactor Coolant System - Issue 4 Revision 4
- D Page IF 39 of 40 Operating Procedure O
'.i v).
.lNSTRUMENT FAILURE PROCEDURE.
V. REFERENCES , A. TECHNICAL SPECIFICATIONS ,
'i. BVPS-2 T.S. 3.3.1.1
- 2. BVPS-2 T.S; Table 3.3.1, items 7 and 8 B. . UPDATED FINAL SAFETY ANALYSIS REPORT
- 1. . UFSAR-2 Section 7.2.1.1.2
- 2. UFSAR-2 Section 7.2.2.3.2 ,
C.' COMMITMENTS , 4: NONE D.~ ADMINISTRATIVE . NONE i E. VENDOR INFORMATION
- 1. 2001.410-001-115,' AT/Tavg Protection i
- 2. 2001.410-001-116, AT/Tavg Protection I G.
k.-( 3. 2001.410-001-125, AT/Tavg Protection 11
- 4. 2001.410-001-126, AT/Tavg Protection 11
- 5. 2001.410-001-137, AT/Tavg Protection ill
- 6. 2001,410-001-138, AT/Tavg Protection ill
- 7. 2001.410-001-227,' AT/Auctioneered. AT Deviation Alarms ,
- 8. 2001.410-001-228 Tavg/ Auctioneer, Tavg Deviation Alarms
^
- 9. 2001.410-001-229,' Hi Tavg/ Tref Deviation
- 10. 2001.410-001-230, Rod Insertion Limits, Banks A and B ,
- 11. '2001.410-001-116, Rod insertion Limits, Banks C and D
- 12. 2001.409-001-021, Functional Diagrams, Primary Coolant System Trip Signals F. DRAWINGS
~
.NONE y
.O L.]f S
ATTACHMENT 4
a c 2OM-6.4.lF ?
. Beaver Valley Power Station Unit 2 issue 4 Revision 4
~ Reactor Coolant System Page' IF 40 of 40
. Operating Procedure '
I '
?/"' ,
5 j INSTRUMENT FAILURE PROCEDURE LG.. OPERATING MANUAL ,
~1. 2OM-6.1,' Reactor Coolant System, Description
- 2. 20M-1.1, Reactor Control and Protection. Description 3
- 3. 20M-1.4.AAT, Loop Tm Deviation ,
' 4. 2OM-1.4.AAU, Loop AT Deviation
- 5. 2OM-1.4.AAV, Tiva Deviation From Tm 6; 20M-1.4.AAW, Loop Overpower AT a
- 7. 2OM-1.4.AAX, Loop Overpower AT Auto-Turb Rnbk Block Rod W/D '
- 8. 2OM-1.4.AAY, Loop Tm High
- 9. 2OM-1.4.AAZ, Loop Overtemperature AT !
j
~ 10. ;2OM-1.4.ABA, Loop Overtemp AT Auto-Turb Rnbk Block Rod W/D
- 11. 2OM-1.5, Reactor Control And Protection, Table 1-6 H'. PLANT MODIFICATIONS
?
LNONE '
- 11. OTHER
- 71. Plant Computer Systems Database Configuration Management Systems Compute input / Output List.
- 2. 2MSP-6.20-1, Reactor Coolant Temperature Loop 2RCS-T412 Delta T-TAVG j Protection Channel i Test f
- 3. 2MSP-6.21-1, Reactor Coolant Temperature Loop 2RCS-T422 Delta T-TAVG '
Protection Channel 11 Test
- 4. 2MSP-6.22-1, Reactor Coolant Ternperature Loop 2RCS-T432 Delta T-TAVG Protection Channel 111 Test
- 5. OMDR 2-93-0181 (Rev.1)
- 6. OMCR 2-94-2070; 2-95-0232 (Rev. 2).
i ,j i r O . ;
'l l
ATTACHMENT J'
RTL #AS.640U BEAVER VALLEY JOB PERFORMANCE MEASURE EVALUATOR COVER SHEET JPM Number: 2CR-529 Rev: 2a System #: 0'06 4 JPM
Title:
Transfer to Cold Leg Recirculation (ES1.3) K/A
Reference:
006020A4.02 3.9/3.8, Task ID #:0060160101 006000A4.02 4.0/3.8 006000G13 3.9/3.4,006A4.05 3.9/3.8, 006A4.02 4.1/3.8, 2.1.23 3.9/4.0 JPM Application: 05 Requal X Initial Exam [] Training Evaluation Method LOCATION TYPE [] Perform [] Plant Site [] Training [] Simulate [] Simulator [3 Annual Requal. Exam [] Classroom [] OJT [] Initial Operator Exam Administered By: [] Other: [] BV-T [] NRC [3 Other: Evaluation Results Performer: Name: Employee No: O Results [3 SAT Time (minutes) [] UNSAT* Allotted: 15 Actual: Time Critical: [] ves DD No Administrative JPM [3 Faulted X
- Comments (Required for UNSAT Evaluation):
4 Evaluation Results [3 Check here if same as above Observer 1: Name: Employee No: Observer 2: Name Employee No: Observer 3: Name Employee No: Observer 4: Name Employee No: Time (minutes) Results Question ID Allotted Actual SAT UNSAT* Question #1 [] [] Employee No: Question #2 [] [] Employee No:
- Comments (Required for UNSAT Evaluation):
O Evaluator (Print): Organization: Evaluator Signature Date: After Val
1 I RTL #AS.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE D (s.j ~ CANDIDATE DIRECTION SHEET
- THIS SHEET TO BE GIVEN TO CANDIDATE
- l Read: l l
Task: Transfer to Cold Leg Recirculation (ES-1.3)
. l INITIAL CONDITIONS: lTheplantisrecoveringfromaLossof Coolant Accident. The control room ]
operators are now into OM-53A, Procedure l ES-1.3 " Transfer to Cold Leg Recirculation" and entered Step 6 of that ; procedure. ("% hs,,/ INIT. CUE: Your supervisor directs you to perform Step 6 of OM-53A, Procedure ES-1.3 " Transfer to Cold Leg Recirculation" I At-this time, ask the evaluator any questions you have on this JPM.* When satisfied that you understand the assighed, task, announce "I am now beginning the JPM".
. Simulate performance or perform as directed the required task.
Point to any indicator or component you verify or check and announce your' observations. After determining the Task has been met, announce "I have completed the JPM". Then hand back this sheet to the evaluator. l . j N_- I-After Val
l ll RTL #AS.635.J . BEAVER VALLEY JOB PERFORMANCE MEASURE EVALUATOR DIRECTION SHEET ,1 JPM NUMBERt 2CR-529 I JPM TITLE: Transfer to Cold Leg Recirculation (ES-1.3) l TASK STAN.: Valve alignments for Cold Leg Recirculation according to Step 6 of OM-53A, Procedure ES-1.3 completed. j RECOMMENDFD STARTING LOCATION: CONTROL ROOM DIRECTIONSt You are to simulate (perform) the task j Transfer to Cold Leg Recirculation (ES-1.3). INIT. CONDITIONS: . The plant is recovering from a Loss.of Coolant Accident. The control room operators are now into OM-53A, Procedure ES-1.3 " Transfer to Cold Leg Recirculation" i}}