ML021610483
| ML021610483 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 05/31/2002 |
| From: | Hackenberg J AmerGen Energy Co |
| To: | Conte R NRC/RGN-I/DRS/OSB |
| References | |
| 05000219/02301 | |
| Download: ML021610483 (4) | |
Text
Oyster Creek Generating Station NRC Operating Examination - May 2002 Validation Changes Admin JPMs 200.OA change tolerance for correct answer from 0.1 to 0.2, step 5 Operational JPMs 201.02 Add cue after step 4, If Reactor Engineer contacted - state that under current conditions it is permissible to follow the ABN actions.
239.01 Change task conditions, add, Plant is in an ATWS condition, crew is preparing to lower level.
202.10 Add second cue after step 1; CUE: the other RO will attend to all alarms not associated with your present task.
NOTE: after step 6, coordinate with/contact electrician directly.
226.01 Corrected Task Conditions (ATWS and LOCA) and incorporated ability to secure recirc pumps and drywell fans.
264.01 Enhanced initiating cue: Load diesel to 2800 KW and adjust KVARS to 1000 KVARS.
Added CUE after step 3, EO may be sent to EDG building.
Step 11 - change to 2800. Add cue after step 11; change to 1000.
261.ON Changed JPM to be consistent with Support Procedure 49 279.06 Made step 5 & 6 NOT critical
Scenario changes SRO#1 Event 5, Add NOTE: Due to a loss of all condensate pumps, an automatic scram on low reactor water level may occur before a manual scram is directed.
Event 8, Changed event description; deleted Manual and added NOTE: EMRV may open automatically due to high reactor pressure. The valve will fail open after either manual or automatic actuation.
SRO#2 Event 2, edit Cause; change shutdown to trip.
Event 4, added review of TS 3.5, Containment Integrity Event 6, add NOTE: The evaluator may direct the leakrate to be increased, if required SRO#3 Event 2, add NOTE: If the candidate checks the Reactor Building ambient temperature (on the back panels), tell him that the ambient temperature is 75 degrees F.
Event 7, Deleted, no replacement required SRO#4 Shift Turnover, eliminated Backup EMRV position indication OOS Event 2, changed TS evaluation description Event 3, changed power limit to 569.5 Mwe Event 6, added Support Procedure references
ES-301 Administrative Topics Outline Form ES-301-1 Facility:
Oyster Creek NRC Date of Examination: Week of May 13, 2002 Examination Level (circle one):
RO /(
i Operating Test Number:
SRO Administrative Topic/Subject Description Temporary Procedure Change JPM Plant Parameter Verification JPM Describe method of evaluation:
- 2. TWO Administrative Questions Temporary Procedure Change - Alternate Path (JPM)
Change of intent 4
Verification of Identified Leakage (JPM)
A.2 Technical Specification Tech Spec interpretation and log entry (JPM)
Equipment Control JPM A.3 Control of Radiation Review and approve a Liquid Radwaste Discharge - Alternate Releases JPM Path (JPM)
Authorize pumping 1-5 sump overboard, SW rad monitor A.4 Emergency Classification Make an Emergency Classification (JPM)
JPM Security based A.1 ES-301 Administrative Topics Outline Form ES-301-1
ES-301 Control Room Systems and Facility Walk-Through Test Outline Facility:
Oyster Creek NRC Date of Examination:
Week of May 13, 2002 Exam Level (circle one): RO /(SRO.ID/ SRO(U)
Operating Test No.:
SRO B.1 Control Room Systems System / JPM Title Type Safety Code*
Function
- a. Reactor Manual Controls (RMC) / Perform rod coupling 201.01 check (Alternate Path - Rod Uncoupled)
M, S, A, L
service N, S
- c. Main Steam I Bypass a MSIV low-low isolation signal 239.01 3
D, S
- d. Recirculation system / Respond to a tripped recirc pump 202.10 4
with 5 operating (Alternate Path - Discharge Valve will not D, s, A close)
- e. Containment Spray / Manually initiate Containment Spray 226.01 5
(Alternate Path - Containment Spray Pump Trips)
M, S, A
- f. Emergency Generators / Normal start of EDG from control 264.01 6
room D, S
- g. Standby Gas Treatment system (SGTS) / Confirm 261.01 9
Secondary Containment Initiations and Isolations (Alternate N, S, A Path - SGTS fails to start) 119' cask ops, RBHVAC trips, SGTS fails to start, verify iso/actuations due to SCC, SP 49.
B.2 Facility Walk-Through 308.04
- a. Shutdown Cooling / Transfer control to LSP 1A2 (shutdown D,R 4
cooling pump)
Abnormal 223.03
- b. Primary Containment / Line-up to vent the Torus through D
5 the hardened vent Emergency 279.06
- c. Instrument Air ! Manually scram the reactor by venting the D, R 8
- Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room, (S)imulator, (L)ow-Power, (R)CA Form ES-301-2