ML17214A104

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2017 Fer Ile Administrative Files Outline and Operating Test Comments
ML17214A104
Person / Time
Site: Fermi DTE Energy icon.png
Issue date: 04/03/2017
From: Bielby M
Operations Branch III
To:
NRC/RGN-III/DRS/OLB
Shared Package
ML17061A771 List:
References
Download: ML17214A104 (3)
v • d • e


Text

NRC ILE Outline and Operating Test Submittal Comments 2017 FER Power Plant, Unit 2 Outline Submittal Comments RO Administrative JPMs Chief Examiner Comment Facility Action/Response COO1: JP-OP-802-4101-446; Was this surveillance administered on either This surveillance is new and was not Complete Mode 4 Shiftly/Daily of the previous 2 NRC exams (2013, 2015) administered on either of the previous 2 NRC Surveillances or the audit exam? or audit exams.

COO2: JP-OP-802-4101-450; Both the RO and SRO perform same COO2 As validated, the original Admin JPM validated Determine the Availability of RPV admin JPM. Please replace at least one poorly and would take at least an hour to Level Instruments admin JPM such that one is SRO and the perform. Replaced with JP-OP-802-4101-431; other RO. Perform Core Performance Parameter Check.

EC: 802-4101-441; Identify Replaced with JP-OP-802-4101-452; Identify Isolation Boundaries for a Isolation Boundaries for Steam Leak. Based on Clearance to Replace Pump feedback from validation crew.

Impeller RC: JP-OP-802-4101-416; Enter Both the RO and SRO perform same RC Replaced with 802-4101-416; Determine and Exit a Contaminated Area admin JPMs. Please replace at least one Dose and Complete a Red Card. Original admin JPM such that one is SRO and the JPM would be difficult to perform during plant other RO. outage.

SRO Administrative JPMs Chief Examiner Comment Facility Action/Response COO1: JP-OP-802-4101-440; Was this surveillance administered on either 1) This surveillance is new and was not Complete Mode 5 Shiftly/Daily of the previous 2 NRC exams (2013, 2015) administered on either of the previous 2 NRC Surveillances or the audit exam? 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 reduces steps from 35 to 6 (decrease JPM time).

COO2: JP-OP-802-4101-450; Both the RO and SRO perform same COO2 As validated, the original Admin JPM Determine the Availability of RPV admin JPM. Please replace at least one validated poorly and would take at least an Level Instruments admin JPM such that one is SRO and the hour to perform. Replaced with JP-OP-802-other RO. 4101-431; Perform Core Performance Parameter Check.

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NRC ILE Outline and Operating Test Submittal Comments 2017 FER Power Plant, Unit 2 RC: JP-OP-802-4101-416; Enter Both the RO and SRO perform same RC Replaced with 802-4101-435; Notify Hospital and Exit a Contaminated Area admin JPMs. Please replace at least one of Contaminated Injured Worker. Original admin JPM such that one is SRO and the JPM would be difficult to perform during plant other RO. outage.

Scenario ES D-1 Chief Examiner Comment Facility Action/Response Scenario 1 Scenario 1 is similar to 2013-1 exam scenario. It was significantly modified.

(ES-301, Section D.5.b). Or was it a spare on 2013 exam?

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NRC ILE Outline and Operating Test Submittal Comments 2017 FER Power Plant, Unit 2 Operating Test Submittal Comments RO/SRO Admin JPMs Comments Chief Examiner Comment Facility Action/Response RO Admin A1.2 JPM Step 2 (16.b.2(b)), Verify.. is not critical. Revised.

COO2: JP-OP-802-4101-431; Perform Core Performance Parameter Check RO Admin A2 Update forms to use current revisions. Recent revision change, updated.

EC: JPM-802-4101-452; Identify Isolation Boundaries for Steam Leak.

RO Admin A3 Change JPM to increase accumulated dose for the JPM modified as described. No change to JPM RC JPM 802-4101-416; year to 1753 mr to allow use of the original survey map steps, only calculation values.

Determine Dose and with much lower dose values to make the JPM more Complete a Red Card believable. JPM was changed from original submittal because the Fermi 2 administrative limit was changed to 2 mr.

SRO Admin A1.2 JPM Step 2 (16.b.2(b)), Verify.. is not critical. Revised.

COO2: JP-OP-802-4101-431; Perform Core Performance Parameter Check 3 of 5

NRC ILE Outline and Operating Test Submittal Comments 2017 FER Power Plant, Unit 2 RO/SRO CR/IP System JPMs Comments Chief Examiner Comment Facility Action/Response Chief Examiner Comment Facility Action/Response SIM JPM S7(g) Incorporate critical JPM Step 3 into Step 2 and make Lic: Incorporated.

JP-OP-802-4101- Step 2 critical. Renumber JPM steps accordingly.

445; SRM/IRM Overlap Verification and SRM Withdrawal During Startup SIM JPM S8(h) JPM Steps 3 and 4 not critical. Lic: Incorporated.

JP-OP-315-0166-002; Restore RBHVAC to Operation After Auto Isolation IP JPM P3(k) NRC: In-Plant Systems JPM (k) JP-OP-315-0167- Lic: The change was based on the ALARA principle 005,Shift RBCCW Supplemental Cooling Chilled Water that during licensee validation 3 radiological hot to Mode 2 was changed to Adjust Chilled Water spots were identified in the area of the JPM and Temperature Set-point. during JPM performance significant dose could be obtained.

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NRC ILE Outline and Operating Test Submittal Comments 2017 FER Power Plant, Unit 2 Scenario Comments Chief Examiner Comment Facility Action/Response Scenario 1 1. Incorporate Events 3 and 4 into Event 2 and 1. Incorporated Events 3 and 4 into Event 2 and renumber events. renumbered events.

2. Event 5, add TS condition. 2. Added TS condition to Event 5 (now Event 3).
3. Event 7, add TS condition, move CT 1, RPV- 3. Added TS condition to Event 7 (now Event 5).

LEVEL, to Event 10, Drywell Leak. Moved CT 1 to new Event 7 (Drywell Leak).

4. Event 9, rename CT 2, RPV-ED, and move to 4. Renamed and moved CT 2 to new Event 7 Event 10, Drywell Leak. (Drywell Leak).
5. Event 10, rename CT 3, RPV-TAF. 5. Renamed CT 3, now part of new Event 7.
6. Event 10, rename CT 4, PC-DWS, and move to 6. Renamed CT 4, now part of new Event 8.

Event 12. Delete CT 5. Deleted CT 5.

Scenario 2 1. Event 2, add conditions to each of the 4 TSs. 1. Added conditions to TSs, incorporated Event 3 Combine Event 3 into Event 2. into Event 2, and renumbered events.

2. Event 5, delete CT 1 to reduce power with CRAM 2. Deleted CT 1 for Event 5 (new Event 4).

Array rods. 3. Incorporated comment (now CT 1, ATWS-ADS,

3. Relabel CT 2 as CT 1, ATWS-ADS. new Event 5).
4. Relabel CT 3 as CT 2, ATWS-SLC. 4. Incorporated comment (now CT 2, ATWS-SLC,
5. Relabel CT 4 as CT 3, ATWS-RODS. new Event 6).
6. Relabel CT 5 as CT 4, ATWS-T&P, and add CT 5, 5. Incorporated comment (now CT 3, ATWS-RODS, ATWS-INJ. new Event 7).
6. Incorporated comment (now CT 4, ATWS-T&P, and CT 5, ATWS-INJ, new Event 8).

Scenario 3 1. Event 2, change event to have rod drift out, vices, into 1. Incorporated comment.

the core. More significant reactivity event, but will lose 2. Incorporated comment.

the TS. 3. Incorporated comment.

2. Incorporate Event 4 into Event 3 and renumber Events. Add condition to TR.
3. Event 5, delete TS.

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