ML17214A104
| ML17214A104 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 04/03/2017 |
| From: | Bielby M E Operations Branch III |
| To: | NRC/RGN-III/DRS/OLB |
| Shared Package | |
| ML17061A771 | List: |
| References | |
| Download: ML17214A104 (3) | |
Text
NRC ILE Outline and Operating Test Submittal Comments 201 7 FER Power Plant, Unit 2 1 of 5 Outline Submittal Comments RO Administrative JPMs Chief Examiner Comment Facility Action/Response COO1: JP-OP-802-4101-446; Complete Mode 4 Shiftly/Daily Surveillances Was this surveillance administered on either of the previous 2 NRC exams (2013, 2015) or the audit exam?
This surveillance is new and was not administered on either of the previous 2 NRC or audit exams
. COO2: JP-OP-802-4101-4 50; Determine the Availability of RPV Level Instruments Both the RO and SRO perform same COO2 admin JPM. Please replace at least one admin JPM such that one is SRO and the other RO. As validated, the original Admin JPM validated poorly and would take at least an hour to perform. Replaced with JP-OP-802-4101-431; Perform Core Performance Parameter Check.
EC: 802-4101-441; Identify Isolation Boundaries for a Clearance to Replace Pump Impeller Replaced with JP-OP-802-4101-452; Identify Isolation Boundaries for Steam Leak. Based on feedback from validation crew.
RC: JP-OP-802-4101-4 1 6; Enter and Exit a Contaminated Area Both the RO and SRO perform same RC admin JPMs.
Please replace at least one admin JPM such that one is SRO and the other RO. Replaced with 802
-4101-416; Determine Dose and Complete a Red Card.
Original JPM would be difficult to perform during plant outage. SRO Administrative JPMs Chief Examiner Comment Facility Action/Response COO1: JP-OP-802-4101-44 0; Complete Mode 5 Shiftly/Daily Surveillances Was this surveillance administered on either of the previous 2 NRC exams (2013, 2015) or the audit exam?
- 1) This surveillance is new and was not administered on either of the previous 2 NRC or audit exams
. 2) Modified to JP-OP-802-4101-440; Review Mode 5 Shiftly/Daily Surveillances (PMT). Determination of component operability is more of an SRO function
, and also reduce s steps from 35 to 6 (decrease JPM time).
COO2: JP-OP-802-4101-4 50; Determine the Availability of RPV Level Instruments Both the RO and SRO perform same COO2 admin JPM. Please replace at least one admin JPM such that one is SRO and the other RO. As validated, the original Admin JPM validated poorly and would take at least an hour to perform.
Replaced with JP-OP-802-4101-431; Perform Core Performance Parameter Check.
NRC ILE Outline and Operating Test Submittal Comments 201 7 FER Power Plant, Unit 2 2 of 5 RC: JP-OP-802-4101-4 1 6; Enter and Exit a Contaminated Area Both the RO and SRO perform same RC admin JPMs. Please replace at least one admin JPM such that one is SRO and the other RO. Replaced with 802
-4101-435; Notify Hospital of Contaminated Injured Worker.
Original JPM would be difficult to perform during plant outage. Scenario ES D
-1 Chief Examiner Comment Facility Action/Response Scenario 1 Scenario 1 is similar to 2013
-1 exam scenario. (ES-301, Section D.5.b). Or was it a spare on 2013 exam?
It was significantly modified
.
NRC ILE Outline and Operating Test Submittal Comments 201 7 FER Power Plant, Unit 2 3 of 5 Operating Test Submittal Comments RO/SRO Admin JPMs Comments Chief Examiner Comment Facility Action/Response RO Admin A1.2 COO2: JP-OP-802-4101-431; Perform Core Performance Parameter Check JPM Step 2 (16.b.2(b)), "Verify-.." is not critical.
Revised. RO Admin A2 EC: JPM-802-4101-452; Identify Isolation Boundaries for Steam Leak. Update forms to use current revisions.
Recent revision change, updated.
RO Admin A3 RC JPM 802-4101-416; Determine Dose and Complete a Red Card Change JPM to increase accumulated dose for the year to 1753 mr to allow use of the original survey map with much lower dose values to make the JPM more believable. JPM was changed from original submittal because the Fermi 2 administrative limit was changed to 2 mr. JPM modified as described. No change to JPM steps, only calculation values.
SRO Admin A1.2 COO2: JP-OP-802-4101-431; Perform Core Performance Parameter Check JPM Step 2 (16.b.2(b)), "Verify-.." is not critical.
Revised.
NRC ILE Outline and Operating Test Submittal Comments 201 7 FER Power Plant, Unit 2 4 of 5 RO/SRO CR/IP System JPMs Comments Chief Examiner Comment Facility Action/Response Chief Examiner Comment Facility Action/Response SIM JPM S7(g) JP-OP-802-4101-445; SRM/IRM Overlap Verification and SRM Withdrawal During Startup Incorporate critical JPM Step 3 into Step 2 and make Step 2 critical. Renumber JPM steps accordingly.
Lic: Incorporated.
SIM JPM S8(h) JP-OP-315-0166-002; Restore RBHVAC to Operation After Auto Isolation JPM Steps 3 and 4 not critical.
Lic: Incorporated.
IP JPM P3(k) NRC: In-Plant Systems JPM (k) JP
-OP-315-0167-005,"Shift RBCCW Supplemental Cooling Chilled Water to Mode 2" was changed to "Adjust Chilled Water Temperature Set
-point". Lic: The change was based on the ALARA principle that during licensee validation 3 radiological hot spots were identified in the area of the JPM and during JPM performance significant dose could be obtained.
NRC ILE Outline and Operating Test Submittal Comments 201 7 FER Power Plant, Unit 2 5 of 5 Scenario Comments Chief Examiner Comment Facility Action/Response Scenario 1 1. Incorporate Events 3 and 4 into Event 2 and renumber events.
- 2. Event 5
, add TS condition.
- 3. Event 7, add TS condition, move CT 1, RPV-LEVEL, to Event 10, Drywell Leak
. 4. Event 9, rename CT 2, RPV-ED, and move to Event 10, Drywell Leak.
-TAF. 6. Event 10, rename CT 4, PC
-DWS, and move to Event 12. Delete CT 5.
- 1. Incorporated Events 3 and 4 into Event 2 and renumbered events.
- 2. Added TS condition to Event 5 (now Event 3).
- 3. Added TS condition to Event 7 (now Event 5). Moved CT 1 to new Event 7 (Drywell Leak). 4. Renamed and moved CT 2 to new Event 7 (Drywell Leak).
- 5. Renamed CT 3, now part of new Event 7.
- 6. Renamed CT 4, now part of new Event
- 8. Deleted CT 5.
Scenario 2 1. Event 2, add conditions to each of the 4 TSs. Combine Event 3 into Event
- 2. 2. Event 5, delete CT 1 to reduce power with CRAM Array rods.
-ADS. 4. Relabel CT 3 as CT 2, ATWS
-SLC. 5. Relabel CT 4 as CT 3, ATWS
-RODS. 6. Relabel CT 5 as CT 4, ATWS
-T&P, and add CT 5, ATWS-INJ. 1. Added conditions to TSs, incorporated Event 3 into Event 2, and renumbered events.
- 2. Deleted CT 1 for Event 5 (new Event 4).
-ADS, new Event 5).
-SLC, new Event 6).
-RODS, new Event 7).
-INJ, new Event 8).
Scenario 3 1. Event 2, change event to have rod drift out, vices, into the core. More significant reactivity event, but will lose the TS. 2. Incorporate Event 4 into Event 3 and renumber Events. Add condition to TR.
- 3. Event 5, delete TS.
- 1. Incorporated comment.
- 2. Incorporated comment.
- 3. Incorporated comment.