ML20031D464
| ML20031D464 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 07/01/1977 |
| From: | Crosby J NORTHEAST NUCLEAR ENERGY CO. |
| To: | |
| Shared Package | |
| ML20031D456 | List:
|
| References | |
| RTR-NUREG-0619, RTR-NUREG-619 SP-631.2, NUDOCS 8110130365 | |
| Download: ML20031D464 (5) | |
Text
l AppgoyAt. xhC 9
DATE:
7_- 1 _77 '
s Plant Superintendent STATION PROCEDURE COVER SHEET A.
IDENTIFICATION Number SP 631.2
- ney, 4
Title CONTROL R0D EXERCIS.E - STUCK CONTROL RODS Prepared By J. Crosby B.
REVIEW I have reviewed the above procedure and have found it to be satisfactory.
TITLE SIGNATURE DATE DEPARTilE!!T HEAD
- 27 Q.
pg y,/p
'/lj RA h
~
n,, m A
co_
\\
C.
UNREVIEMED SAFETY QUESTION EVALUATION 00CUMEllTATION REQUIRED _:
(Significant change in procedure method or scope as described in FSAR)
YES [ 3 NO [4 (If yes, document in PORC/SORC meeting minutes)
Et1VIRONMENTAL IMPACT (Adverseenvironmentalimpact)
YES [ ]
NO ((
(If yes, document in PORC/SORC meeting minutes)
D.
PORC/SbRCAPPROVAL PORC/50RC Meeting Number so-4I E.
APPROVAL AND IMPLEMENTATION The attached procedure is hereby approved, and effective on the dates below:
,e/&
kf)s)'
Nb//D Uh Plant Superintendent / Unit Superintendent Approv6d Date
. Effectife' Date SF-301
!Rev. 2
/ 8110130365 811005 PDR ADOCK 05000245
- P PDR s
e
w-.
--r-
SP 631.2 Page 1 i
Rev. 4 Date: 5/6/80 2
1
,t CONTROL ROD EXERCISE - STUCK CONTROL RODS
'I J
Page No.
Effective Revision Date i
1 4
5/6/80 i
1 2
4 5/6/80 3
4 5/6/80 4
4 5/6/80 I
I l.
I t
J
?
f t
1 I
i a
4 k
4 h
I l
L..
_,,_,,_,_.,__,,,_....,_.,_,_....__,_,-..,_,_..m._
(
SP b31.2 Page 2 Rev. 4 Date: 5/6/80 1.
OBJECTIVE 1.1 To exercise all non-fully inserted control rods, weekly, or 1.2 To exercise all non-fully inserted control rods with three or more non-fully inserted rods electrically disarmed, daily.
2.
ACCEPTANCE CRITERIA 2.1 Proper operation of the non-fully inserted control rods with/
without three or more non-fully inserted control rods electrically disarmed.
3.
REFERENCES 3.1 Technical Specification 4.3. A.2, 3.3.D 3.2 In Service Inspection (ISI) Program 4.
PREREQUISITES 4.1 The Reactor shall be operating at any pressure.
4.2 Test equipment - None.
5.
INITIAL CONDITIONS 5.1 Power Operation 6.
PRECAUTIONS 6.1 At all reactor operating pressures, a rod accumulator may be inoperable provided that no other control rod in the nine-rod square array around this rod has a directional control valve electrically disarmed while in a non-fully inserted position.
6.2 All procedure steps shall be coordinated with the Control Room Operator.
6.3 In no case shall the number of non-fully inserted rods disarmed be greater than eight during power operation.
6.4 When exercising rods, insert rods in one notch and then withdraw to the previous notch so as to avoid an undesired power increase.
(
SP 631.2 Page 3 Rev. 4 Cate: 5/6/80 6.5 This test shall be performed on one rod at a time.
The,following conditions must be satisfied if a control rod is 6.6 to be inserted or withdrawn:
1.
Mode switch shall not be in the SHUTDOWN (scram) position.
2.
RWM rod withdrawal and insertion criteria shall be satisfied.
3.
Control Rod Withdrawal Interlock Circuit shall be energized insuring the Neutron Monitoring and the components of the Scram System are operable.
4.
Sequential Timing Circuit shall be operable.
6.7 For any stuck rod, not in the fully inserted position, notify the Reactor Engineer or his designee, in order that he may evaluate that the shutdown margin requirement is met.
7.
PROCEDURE 7.1 When tne process computer is available, demand an OD7 option 2.
7.2 Select the particular rod to be exercised by momentarily depressing the Rod Select pushbutton on CRP 905.
Continuously monitor nuclear instrumentation during NOTE:
rod movement.
Rotate the Rod Movement Control Switch to the rod in position 7.3 momentarily and release. Verify the rod has settled in-the next even numbered position beft e the rod out settle light extinguishes on CRP 905.
Restore the rod to its original position by rotating the rod 7.4 movement control switch to the R0D OUT NOTCH position momentarily Verify the rod has settled in the original and release.
position before the ROD OUT SETTLE light extinguishes.
If the rod should continue to withdraw past its NOTE:
original position:
If a timer malfunction is observed inanediately a-initiate control rod insert by actuating the "Erargency In" switch.
(
SP 631.2 Page 4 Rev. 4 Date:5/6/80 b-If a time malfunction is not observed rotate the norel r:d movement control switch to the In position.
If the control rod drive does not respond scram c
the malfunctioning rod from CRP 916 to insert the rod.
d-If the rod continues to demonstrate occurrences of inadvertant withdrawal the rod should be fully inserted and valved out of service per OP 302. After the rod is valved out the associated j
122 valve and its controi circuitry should be checked out and repaired.
g If the reactor is at power and the rod is fully e-inserted the Duty Reactor Engineer should be notified immediately to provide guidance relative to the fuel performance limits.
7.5 Repeat steps 7.1 through 7.4 for all non-fully inserted rods.
7.6 Record the control rod exercising on the Shift Surveillance Schedule (1-0PS-10.10) when required.
7.7 Complete OPS Form 631.2-1.
7.8 Discrepancies shall be recorded on the Control Rod Drive Surveillance Program Log.
8.
RESTORATION Demand an OD7 option 2 from the process computer (if available) 8.1 and compare present rod position with previous rod position to ensure all rods are restored to their original position.
9.
SURVEILLANCE DATA SHEET 9.1 OPS Form 631.2-1 JC:kaf
_-