ML20031D468
| ML20031D468 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 06/18/1980 |
| From: | Berry E NORTHEAST NUCLEAR ENERGY CO. |
| To: | |
| Shared Package | |
| ML20031D456 | List:
|
| References | |
| RTR-NUREG-0619, RTR-NUREG-619 SP-631.4, NUDOCS 8110130370 | |
| Download: ML20031D468 (5) | |
Text
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S c ndt-nt STATION PROCEDURE COVER SHEET L
IDEXU D CAT 10ti,
Number SP 631..A ____.._._____ _______._
Rev.
3_
CONTROL R0D INTEGRITY AND Title NUCLEAR INSTRUMENTATION DISCERNIBLE RESPONSE VERIFICATION P r ep a r e d By_ _ _E._. B e rg_ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _
3.
, REVIEW I have reviewed the above procedure and have found it to be satisfactory.
TIILE SIGNATURE DATE dT' 2 A //
DEPARTMENT _ HEAD
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U"REVIEUED SAFETY QUESTION EVALUATION DOCUMENTATION _ REQUIRED:
(Significant change in procedure method or scope f
as described in FSAR)
YES [ ]
N0 [*]
(If yes, document in PORC/SORC meeting minutes)
ENVIR'JNMENTAL IMPACT (Adverse environmer '..I impact)
- YES [ ]
NO [
(If yes, document in PORC/50RC meeting minutes)
PORC/SORC APPROVAL PORC/SCRC Meeting Number 7/-21 APPROVAL AND IMPLEMENTATION o
The attached procedure is hereby approved, and effective on the dates below:
n/u/
shM zMn Station Superintendent,., nit Superintendent Appfovdd Date Eff6ctife Date l
SF-301 Rev. 3 K obohs PDR
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SP 631.4 Page 1 Rev. 3 Date: 2/20/81 C_0NTROL R0D INTEGRITY AtlD 0
@ CLEAR INSTRUl1ENTATION DI3CERN_IBLE RESPONSE VERIFICATION Page No.
Eff. Rev.
Date 1
3 2/20/81 2
3 2/20/81 3
3 2/20/81 4
3 P/P0/81 e
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SP 631.4 Page 2 Rev. 3 Date:2/20/81 1.
OBJECTIVE To verify a discernible response of the nuclear instrumentation when e$ercising the control rods if the initial withdraw after each refueling outage,or after maintenance fails to provide a discernible response of the nuclear instrumentation.
2.
ACCEPTANCE CRITERIA When each rod is exercised / withdrawn, it shall initiate a discernible response on the nuclear instrumentation.
3.
REFERENCES 3.1 Technical Specification 4.3.B.l.b 3.2 Operating Procedure SP 690C 4.
PREREQUISITES 4.1 The CRD System shall be operable as per Operating Precedure 302.
4.2 The SRM's shall be operable as per Operating Procedure 401.
4.3 The IRM's shall be operable as per Oparating Procedure 402.
4.4 The LPRM's shall be operable as per Oparating Procedure 403.
4.5 The APRM's shall be 30erable as per Operating Procedure 404.
4.6 Test equipment - none.
5.
INITIAL CONDITIONS Obtain permission from the Shift Supervisor (SS) or Supervising 5.1
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Control Operator (SCO) for authorization to commence testing.
SS or SCO to initial Data sheet indicating his permission is granted.
The reactor shall be in the Startup or Run mode subsequent to 5.2 a refueling outage.
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SP 631.4 Page 3 Rev. 3 Date:2/20/81 6.
PRECAUTIONS 6.1 All procedure steps shall be coordinated with the Control Room Operator.
7.
PROCEDURE Init".ol data sheet, OPS Form 631.4-1, indicating Prcrequisites 7.1 a.
an) Initial Conditions are met and Precautions noted, Initial on each individual data sheet those rods which b.
were verified by SP 690C.
7.2 Select the control rod to be vithdrawn on CRP-905 in accordance with the Reactor Engineer's approved sequence.
N_03:
For initial rods, Nuclear Instrument Response may not be discernible while the reactor is subcritical.
For such rods, a rod exercise must be performed a convenient time after criticality is achieved and at that time discernible instrument response is verified.
7.3 Withdraw the control rod in accordance with Operating Procedure I
201, Approach to Criticality.
Observe the response for the control rods selected by the Reactor Engineer of any of the following nuclear instrumentation during rod withdrawal depending on the power level:
1.
SRM Level Meter (CRP-936) 2.
SRM Period Meter (CRP-936) 3.
IRM Level Mr ter (CRP-936) 4.
LPRM Level Meter (CRP-937) 5.
APRM Level Meter (CRP-937) 7.4 Record the results of the Nuclear Instrumentation Discernible Response check on the Control Room Coupling Integrity Check Data Sheet, OPS Form 631.4-1, Pages 2 through 14.
7.5 Repeat Steps 7.2 through 7.4 for the remaining control rods.
7.6 Log completion of test in Shift Supervisor's Log.
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SP 631.4 Page 4 l
Rev. 3 Date: 2/20/81 8.
RESTORATION t
8.1 Assure all control rods are returned to the positions as i
I required by Reactor Engineering directive.
i 9.
- SURVEILLANCE DATA SHEETS 9.1 OPS Form 631.4-1, pages 1-14.
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