ML24019A117
| ML24019A117 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 09/28/2021 |
| From: | King J Tennessee Valley Authority |
| To: | NRC/NRR/DORL/LPL2-2 |
| Green K, NRR/DORL/LPL2-2 | |
| Shared Package | |
| ML24019A097 | List: |
| References | |
| Download: ML24019A117 (1) | |
Text
Browns Ferry Nuclear Plant Unit 2 Surveillance Procedure 2-SR-3.1.3.5(A)
Control Rod Coupling Integrity Check Revision 0026 Quality Related Level of Use: Continuous Use Level of Use or Other Information: P2308 Effective Date: 09-28-2021 Responsible Organization:
RXE, Reactor Engineering Prepared By:
Jesse V King Approved By:
Bill Williamson
BFN Unit 2 Control Rod Coupling Integrity Check 2-SR-3.1.3.5(A)
Rev. 0026 Page 6 of 362 1.2 Scope (continued)
This procedure and / or Attachment 1 may be used to record, document, or plan rod movements that otherwise do not require its performance. Those rod movements not required to be recorded by this procedure are:
x Rod moves to SCRAM the reactor.
x Rod moves to check the operability of the RWM.
x Rod moves to correct for a deviation from the RWM.
x Rod moves for CRD exercise testing per 2-SR-3.1.3.3.
x Rod moves for CRD testing per 0-TI-20 whenever not in Modes 1 or 2.
x Rod moves for CRD coupling integrity checks after refueling or maintenance per 2-SR-3.1.3.5(B).
1.3 Frequency Each time a control rod is moved except as specified in Section 1.2 by bulleted items immediately above.
1.4 Applicability Modes 1 and 2. (SR 3.1.3.5)
Modes 1 and 2 whenever the RWM is inoperable with Thermal Power d10%.
Mode 5 with the reactor mode switch in startup/hot standby position. (SR 3.10.8.3)
BFN Unit 2 Control Rod Coupling Integrity Check 2-SR-3.1.3.5(A)
Rev. 0026 Page 15 of 362 (Page 1 of 2)
Control Rod Movement and Control Rod Drive Problem Data Sheets Date ________
Part 1: CONTROL ROD MOVEMENT DATA SHEET RWM1 GP STEP NUMBER ROD NUMBER FROM TO Rod Movement Completed Signoffs UO (AC) 2 Peer Check 3 REMARKS4:
NOTES:
1 RWM Group may be marked "N/A" when NOT applicable (i.e., when above the LPSP).
2 For all rod moves to the "full out" position (notch position 48), this signoff verifies coupling integrity was checked in accordance with 2-OI-85.
3 Documentation of Peer Check by a second qualified member of the plant staff (i.e., RE, STA OR UO) is required ONLY when the RWM is inoperable OR bypassed with core thermal power d10%.
4 Record the rod number and any problems encountered on Attachment 1, page 2 of 2, as applicable.
5 Peer Check by RE OR SRO [SRO to be utilized if a second RE is unavailable]. The SRO should be checking the FROM and TO control rod positions as a minimum. The RE OR SRO should be checking the positions identified for agreement with the Predictor Cases. Anytime the SRO feels the Peer Check is beyond his/her knowledge level, then call-in a second RE to perform the required Peer Check.
Prepared By:
/
Reviewed By5:
/
Reactor Engineer Date RE OR SRO Date Authorization to perform the Control Rod manipulations identified on this sheet
/
Unit SRO Date
BFN Unit 2 Control Rod Coupling Integrity Check 2-SR-3.1.3.5(A)
Rev. 0026 Page 16 of 362 (Page 2 of 2)
Control Rod Movement and Control Rod Drive Problem Data Sheets Date ________
Part 2: CONTROL ROD DRIVE PROBLEM DATA SHEET Control Rod DP Values (See Note)
Control Rod Positions D
N D
A R
S F
I F
W S
F NOTES/OTHER Init DP Reqd DP Init Final
()
()
()
()
()
()
Explain briefly or indicate work orders, PERs, and other documents written to disposition CRD problem q Additional sheets may be used as necessary.
q No entry is required if control rod movement was satisfactory and no other problems were noted.
q Log the initial DP, then the required (elevated) DP at which the Control Rod was successfully moved.
q Indicate CRD Movement problems and any other pertinent facts such as initial and/or final rod positions and drive pressures.
q Record in Condition Report Location Description BFN-2-CRDM-085-XX-YY, where XX-YY are the control rod coordinates.
- Operational problems with CRDs should be documented in a Condition Report including, but not limited to, having to increase Drive Water Pressure to move rod.
DN Double Notched Rod - Indicate control rod movement (i.e., 48 to 44). Do NOT count as DN when elevated drive water DP is used.
DA Drift Alarm - Note any movement of control rod.
RS Problem with RPIS system - List rod position when incident occurred and details.
FI Failed latch at next position on Insert - Indicate initial and final or increased DP.
FW Failed Withdraw - Indicate initial and final or increased DP in the space provided.
SF Stall flow greater than 5 gpm.
BFN Unit 2 Control Rod Coupling Integrity Check 2-SR-3.1.3.5(A)
Rev. 0026 Page 17 of 362 (Page 1 of 39)
A1 Startup Sequence Control Rod Movement Data Sheet Date ________
RWM GP STEP NUMBER ROD NUMBER FROM TO Rod Movement Completed Signoffs UO (AC) 1 Peer Check 2 1
1 58-31 00 48 1
2 34-07 00 48 1
3 02-23 00 48 1
4 18-55 00 48 1
5 50-39 00 48 1
6 18-07 00 48 1
7 02-39 00 48 1
8 34-55 00 48 1
9 50-23 00 48 1
10 10-15 00 48 1
11 10-47 00 48 1
12 42-47 00 48 SRM-B 1
13 42-15 00 48 1
14 10-31 00 48 1
15 26-47 00 48 1
16 42-31 00 48 1
17 26-15 00 48 1
18 18-39 00 48 1
19 34-39 00 48 1
20 34-23 00 48 1
21 18-23 00 48 SRM-D 1
22 26-31 00 48 REMARKS3:
NOTES:
1 For all rod moves to the "full out" position (notch position 48), this signoff verifies coupling integrity was checked in accordance with 2-OI-85.
2 Documentation of Peer Check by a second qualified member of the plant staff (i.e., RE, STA OR UO) is required ONLY when the RWM is inoperable OR bypassed with core thermal power 10%.
3 Record the rod number and any problems encountered, as applicable.