ML101520331

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Final Outlines (Folder 3)
ML101520331
Person / Time
Site: Salem  PSEG icon.png
Issue date: 04/20/2010
From:
Public Service Enterprise Group
To: David Silk
Operations Branch I
Hansell S
Shared Package
ML092470038 List:
References
U01764
Download: ML101520331 (9)
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Text

ES-301 Administrative Outline Form ES-301-1 i

Facility: SALEM Date of Examination: 05/10/10 Examination Level: RO

  • SRO Operating Test Number: 08-01 NRC I

Administrative Describe activity to be performed  !'

Type Topic (See Note)

Code*

Conduct of  ! Operate the Chilled Water System (Identify and Isolate Non-Essential Heat Loads)

R,D Operations

  • 2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc.

Evaluate a shift staffing situation and take corrective action lAW administrative Conduct of ' procedures R,M Operations I 2.1.5 Ability to use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc.

Walkdown control console and determine most limiting LCO for current Mode of

' operation.

Equipment Control S,N

, 2.2.42 Ability to recognize system parameters that are entry level conditions for Technical Specifications SRO 4.6 Authorize a Radioactive Gas Release.

Radiation Control R,D,P 2.3.6 Ability to approve release permits SRO-3.B Emergency Plan S,M Classify Emergency I Non-Emergency Events, and complete the ICMF.

2.4.29 Knowledge of the Emergency Plan SRO 4.4 I

NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.

  • Type Codes and Criteria (C)ontrol Room, (S)imulator, or Class(R)oom (D)irect from bank, (3 for ROs; 4 for SROs & RO retakes)

I (N)ew or (M)odified from bank (1)

(P)revious 2 exams (1; randomly selected)

II

ES-301 Administrative Outline Form ES-301-1 Facility: SALEM Date of Examination: 05/10/10 Examination Level:

  • RO SRO Operating Test Number: 08-01 NRC Adm inistrative Describe activity to be performed Type Topic (See Note)

Code*

Conduct of Perform a RCS Manual Leak Rate Calculation R,M Operations 2.1.18 Ability to make accurate, clear, and concise logs, records, status boards, and reports. RO-3.6 Calculate Quadrant Power Tilt Ratio Conduct of 2.1.43 Ability to use procedures to determine the effects on reactivity of plant R,M Operations changes, such as reactor coolant temperature, secondary plant, fuel depletion, etc.

R04.1 Perform a peer check of an ECC using Nuclear Design Data.

Equipment Control R,M 2.2.1 Ability to perform pre-startup procedures for the facility, including operating those controls associated with plant equipment that could affect reactivity. RO 4.5 Perform Stay Time calculation for Emergency condition.

Radiation Control R, N 2.3.4 Knowledge of radiation exposure limits under normal and emergency conditions. RO-3.2 Emergency Plan N/A N/A NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.

  • Type Codes and Criteria (C)ontrol Room, (S)imulator, or Class(R)oom (D)irect from bank, (3 for ROs; 4 for SROs & RO retakes)

(N)ew or (M)odified from bank (1)

(P}revious 2 exams (1; randomly selected)

ES-301 Control Room Outline Form ES-301-2 SALEM Date of Examination: 05/10/10 SRO-I SRO-U Operating Test No.: 08-01 NRC Systems@ (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U, including 1 ESF)

System I

a. Respond to successive dropped power (003 AA2.03 RO-3.6 SRO-3,8) D,S,A
b. Perform EOP-TRIP-'I Immediate Actions and initiate Safety Injection based on board indication after auto SI fails to actuate (Normal Rx trip from 20%

power entering an outage and fail steam dumps open with no first out of SI) A,EN,N 2 (013 A4.03 RO-4.0 SRO-3.8)

c. Respond to an unwarranted PZR Overpressure Protection System (POPS) actuation. 0 A4.03 RO-4.0 A,N,L 3
d. to a Shutdown LOCA (2.4.9 RO-3.B SRO-4.2) D,S,L 4 (pri) e, Perform stroke time testing of 21 MS167 (Main Steamline Isolation Valve)

(039 A4.01 RO-2.9 SRO-2.8) D,EN,S 4 (sec)

f. Perform a CFCU Operability and Service Water Flow Verification A4.01 RO-3.6 D,S,P 5 Start an EDG from the control room and energize an isolated vital bus (064 A4.01 RO-4.0 SRO-4.3) L,N,S 6 Failure of Permissive P-6 to block Source Range Hi Flux trip during Rx SfU i 012 A4.03 RO-3.6 A, D, L, S 7 (APE 068 AA1.02 RO-4.3 SRO-4.5) D, E, R 4 (sec)
j. Start the SBO Air Compressor (2.1.23 RO-4.3 SRO-4.4) D,E 8
k. Commence a liquid waste release, and respond to high activity during the release D, R,A,P 9 (2.3.11 RO-3.B

@ All RO and SRO-I control room (and in plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may r\\lQrl",n the control room.

(A)lternate path 4-6/ 4-6 I 2-3 (C)ontrol room (D)irect from bank  :=.9 / :=.8 /<4 (E)mergency or abnormal in-plant ~1 / >1/>1 (EN}gineered safety feature - / / > 1 (control room system)

(L}ow-Power I Shutdown / ~1 / ~1 (N)ewor (M)odified from bank including 1 (A) ~2 / ~2/~1 (P)revious 2 exams ,::::,3 / < 3 / < 2 (randomly selected)

(R)CA ~ 1 / := 11 > 1 Simulator

ES-301 Control Room Outline Form ES-301-2 Facility: SALEM Date of Examination: 05/10/10 Exam Level : RO IliSRO-II~ SRO-U Operating Test No.: 08*01 NRC Control Room Systems@ (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U, including 1 ESF)

System I JPM Title Safety Function 1---- - - - - - - - - - - - - - - . - - - - - - - - - - - - - - - ---1-------":---------1

a. Respond to successive dropped control rods at power (003 AA2.03 RO-3.6 SRO-3.8) D,S,A 1
b. Perform EOP-TRIP-1 Immediate Actions and initiate Safety Injection based on board indication after auto SI fails to actuate (Normal Rx trip from 20%

power entering an outage and fail steam dumps open with no first out of SI) A. EN, N 2 11---_-->..(O-=-1c..;:3..:...A.4.03 RO-4.0 SRO-3.8)

c. Respond to an unwarranted PZR Overpressure Protection System (POPS) actuation. 0 A4.03 RO-4.0 A,N,L 3
d. Respond to a Shutdown LOCA

. D,S,L 4 (pri)

~

(2.4.9 RO-3.8 SRO-4.2) e.

. f. Perform a CFCU Operability and Service Water Flow Verification A4.01 RO-3.6 S D,S,P 5 L,N,S 6 D, R, A,P 9

@ All RO and SRO-I control room (and in plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in Criteria for RO / SRO-II SRO-U (A)lternate path 4-6 I 4-6 / 2-3 (C)ontrol room (D)irect from bank .-=:9 I <8 I,-=:4

{E}mergency or abnormal in-plant  :::1 / >1/>1 (EN)gineered safety feature - I - / > 1 (control room system)

(L)ow-Power / Shutdown  :::1 1:::1 I (N)ewor (M)odified from bank including 1 (A)  :::2 / ~2/:::1 (P)revious 2 exams < 3 / .-=: 3 I .-=: 2 (randomly selected)

(R}CA > 1 J ::: 11 ::: 1 Simulator

ES-301 Control Room Systems/In-Plant System Outline_____Form ES-301-2 Date of Examination: 05/10/10 Operating Test No.: 08-01 NRC i Control Room Systems@ (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U, including 1 ESF)

System 1 JPM Title Type Code' 1 Safety Function!

I I

a.

Ir----:---=--:---::::--=-:**-~*.,.-.,--_:c_

b. Perform EOP-TRIP-1 Immediate Actions and initiate Safety Injection based on board indication after auto SI fails to actuate (Normal Rx trip from 20%

power entering an outage and fail steam dumps open with no first out N c.

d.

4 (pri) e.

f.

g.

~-~-*--*~---~*=---~-~~~~-+----~--~------~I

h. Failure of Permissive P-6 to block Source Range Hi Flux trip during Rx S/U (012 A4.03 RO-3.6 SRO-3.6)

In-Plant Systems (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U) i.

8 during the D, R,A,P 9

@ All RO and SRO-I control room (and in plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may ovenap those tested in "Type Codes: ----'

Criteria for RO 1 SRO-I 1 SRO-U (A)lternate path 4-6 1 4-6 1 2-3 (C)ontrol room (D)irect from bank <9 / <8 1.:::4 (E)mergency or abnormal in-plant >1/.::::.1/>1 (EN)gineered safety feature / .: : . 1 (control room system)

(L)ow-Power 1 Shutdown .::::.1 1.::::.1 I .::::.1 (N)ewor (M)odified from bank including 1 (A) .::::.2/.::::.2/.::::.1 (P)revious 2 exams < 3 1 < 3 / < 2 (randomly selected)

(R)CA > 1 I > 11 .::::. 1 Simulator

Appendix D Scenario Outline Form ES-D-1 Facility: SALEM 1 & 2 Scenario No.: ESG-1 Op-Test No.: 08-01 NRC Examiners: Operators:

Initial Conditions: 90% power, MOL. 23 SW pp CfT for strainer repair.

Turnover: Raise Rx power to 100%

Event Malt. No. Event Event Type*

No. Description N

CRS/PO 1 R Raise power RO I

2 Tavg channel fails high (Tech Specs)

CRS/RO C #4 SW Bay leak, leak isolation requires isolating all #4 Bay 3

CRS/PO SW pps, with 23SW pp CfT (TS 3.0.3 entry)

C 4 RCP #1 seal degradation leading to failure CRS/RO C 2A 4KV vital bus de-energizes on Rx trip, EDG output bkr 5

CRS/PO does not shut, no SW pumps are running M

6 SBLOCA ALL 7 C SEC controlled equipment fails to start (22 SI pp)

ALL 8 C Loss of Off-Site power after SI reset ALL

  • (N)ormal, (R)eactlvlty, (I)nstrument, (C)omponent, (M)aJor Appendix 0, Page 38 of 39

Appendix D Scenario Outline Form ES-D-1 Facility: SALEM 1 & 2 Scenario No.: ESG-2 Op-Test No: 08-01 NRC Examiners: Operators:

Initial Conditions: 100% power, BOL, PZR level CH III selected for control due to CH I indication problem. Rod Control in manual due to PT-505 channel calibration in progress. 21 Heater Drain Tank pump O/S due to oil leak. 22 Condensate pump has elevated vibration.

Turnover: Reduce power at 30% per hour to 79% in preparation for removing 22 Condensate Pump from service.

Event Malt. No. Event Event Type*

No. Description N

SRO/PO 1 Perform power reduction R

RO NIA 2 CFCU trip (Tech Specs)

CRS I

3a VCT level ch fails high CRS/RO N

3b Re-establish RCS Letdown PO C

4 Operating charging pump cavitation (Tech Specs)

CRS/RO C

5a 22 Cond pump trip, degraded SGFP suction pressure CRS/PO M

5b 23 Cond pump, loss of both SGFPs ALL C

6 MainTurbine fails to trip initially, MSLI successful RO 7 C 21 AFW pump will not start, 22 AFW pp pressure override defeat failure, 23 AFW pp trips. FRHS with condensate CRS/PO pump recovery.

  • (N)ormal, (R)eactlvlty, (I)nstrument, (C)omponent. (M)aJor Appendix D. Page 38 of 39

Appendix D Scenario Outline Form ES-D-1 Facility: SALEM 1 &2 Scenario No.: ESG-3 Op-Test No.: 08-01 NRC Examiners: Operators:

Initial Conditions: 4.8% power, MOL, Main Turbine is on the Turning Gear. Rx startup by Control Rods was performed. 2PR1 PZR PORV is leaking, 2PR6 is shut with power applied to comply with Tech Specs.

Turnover: Raise Rx power to 17% over the next 30 minutes in preparation for rolling the Main Turbine.

Reactivity plan developed by Rx Engineering directs raising power with control rods only Event Malf. No. Event Event Type*

No. Description N

CRS/PO 1 Raise Rx power R

RO 2 I PZR pressure instrument fails high (Tech Spec)

CRS/RO 3 C ECCS Accumulator low pressure (Tech Specs)

CRS/PO 4 M Rapid degradation of condenser vacuumlloss of steam ALL dumps with power above capacity of SG Atmospheric reliefs.

C Rod Control failure results in no inward rod movement or Rx 5

CRS/RO trip available - ATWT I FRSM 6 C Rapid Borate Stop valve fails to open CRS/RO C

7 PZR PORV fails open.

CRS/RO

  • (N)ormal, (R)eactlvlty, (I)nstrument, (C)omponent, (M)aJor Appendix 0, Page 38 of 39

Appendix D Scenario Outline Form ES-D-1 Facility: SALEM 1 & 2 Scenario No.: ESG-4 (Spare) Op-Test No.: 08-01 NRC Examiners: Operators:

Initial Conditions: Rx power is 67%, BOL. Power is reduced due to 21 MS29 Main Turbine Governor Valve failed shut 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> ago. 2PS1 is leaking and its manual isolation valve is shut. 2PR1 is leaking and its block valve is shut with power applied Turnover: Maintain current power while 21 MS29 failure is investigated.

Event Malf. No. Event Event Type*

No. Description I

1 Controlling PZR level channel fails low (Tech Specs)

ALL 00 2 turbine governor valve (23MS29) fails closed 2 N ALL Power reduction to <30% power (Tech Spec-AFD)

C 3 Steam leak downstream of MSIVs RO C

4 Rx fails to trip from trip switch, RTB trip successful RO M

5 Steam rupture with failed open MSIV ALL C

6 22 AFW pp fails to start PO C

7 SGTR following affected SG de-pressurzation CRS/PO

" (N)ormal, (R)eactlVlty, (I)nstrument. (C)omponent. (M)ajor Appendix D, Page 38 of 39

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