ML18087A733: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(Created page by program invented by StriderTol)
Line 39: Line 39:
* SALEM GENERATING STATION PERFORMANCE DEPARTMENT (I & C) TEST PROCEDURE NUMBER -lPD-18 .1. 004 REV.NO.
* SALEM GENERATING STATION PERFORMANCE DEPARTMENT (I & C) TEST PROCEDURE NUMBER -lPD-18 .1. 004 REV.NO.
DATE PAGE 1 OF 10 TITLE SOLID STATE PROTECTION SYSTEM REACTOR TRIP' BREAKE:R & PERMISSIVE p*-4 TEST -TRAIN A 1.0 Purpose 1.1 To verify the operability of the Reactor Trip Breakers to satisfy requirements of the Technical Specifications . . 1.2 To verify the operability of the Reactor Trip Breaker/ Reactor Bypass Breaker P-4 permissive switches.
DATE PAGE 1 OF 10 TITLE SOLID STATE PROTECTION SYSTEM REACTOR TRIP' BREAKE:R & PERMISSIVE p*-4 TEST -TRAIN A 1.0 Purpose 1.1 To verify the operability of the Reactor Trip Breakers to satisfy requirements of the Technical Specifications . . 1.2 To verify the operability of the Reactor Trip Breaker/ Reactor Bypass Breaker P-4 permissive switches.
: 1. 3 To satisfy the. recommendations o*f Westinghouse Letter PSE-80-14.  
: 1. 3 To satisfy the. recommendations o*f Westinghouse Letter PSE-80-14.
 
2.0 References 2.1 Solid State Protection System Manual 2.2 Westinghouse Letter PSE-80-14 (2/22/80) 2.3 Wiring Diagrams -203688, 222885, 224305, 203646 2.4 Technical Specifications 3.0 Precautions 3.1 Insure that all required safety precautions and tagging procedures have *been complied with as stated in the Performance Department Manual . I Ill C
===2.0 References===
 
===2.1 Solid===
State Protection System Manual 2.2 Westinghouse Letter PSE-80-14 (2/22/80)  
 
===2.3 Wiring===
Diagrams -203688, 222885, 224305, 203646 2.4 Technical Specifications  
 
===3.0 Precautions===
 
===3.1 Insure===
that all required safety precautions and tagging procedures have *been complied with as stated in the Performance Department Manual . I Ill C
* 001 -**.
* 001 -**.
: ....... -**-*** ........  
: ....... -**-*** ........  
Line 67: Line 55:
OF 10 -TITLE SOLID STATE PROTECTION SYSTEM REACTOR TRIP BREAKER & PEEMISSIYE P-4 TEST*-TRAIN A 6.0 Prerequisites 6.1 The individual assigned to perform *this procedure is qualified to do so in accordance with the Solid State Protection System Qualification Card. Supervisor 6.2 The Senior Shift Supervisor/Shift Supervisor has granted permission to perform this procedure.
OF 10 -TITLE SOLID STATE PROTECTION SYSTEM REACTOR TRIP BREAKER & PEEMISSIYE P-4 TEST*-TRAIN A 6.0 Prerequisites 6.1 The individual assigned to perform *this procedure is qualified to do so in accordance with the Solid State Protection System Qualification Card. Supervisor 6.2 The Senior Shift Supervisor/Shift Supervisor has granted permission to perform this procedure.
Senior Shift Supervisor/Shift Supervisor Date/Time 6.3 Tne Control Operator.is aware of all the alarms and indications that will be affected by the performance of this procedure.
Senior Shift Supervisor/Shift Supervisor Date/Time 6.3 Tne Control Operator.is aware of all the alarms and indications that will be affected by the performance of this procedure.
Control Operator I & C -001 x . : .* ,, ... SALEM GENERATING STATION PERFORMANCE DEPARTMENT (I & C) TEST PROCEDURE NUMBER -REV. NO. DATE lPD-18.1.004 1 6/24/82 PAGE 5 OF 10 TITLE SOLID STATE PROTECTION SYSTEM REACTOR TRIP BREAKER & PERMISSIVE P-4 TEST -TRAIN A 7.0 System Line-Up: The following conditions must be established and/or verified by the Control Operator.  
Control Operator I & C -001 x . : .* ,, ... SALEM GENERATING STATION PERFORMANCE DEPARTMENT (I & C) TEST PROCEDURE NUMBER -REV. NO. DATE lPD-18.1.004 1 6/24/82 PAGE 5 OF 10 TITLE SOLID STATE PROTECTION SYSTEM REACTOR TRIP BREAKER & PERMISSIVE P-4 TEST -TRAIN A 7.0 System Line-Up: The following conditions must be established and/or verified by the Control Operator.
 
7.1 Verify the following breaker line-up: 7 .1.1 Reactor Trip Breaker A CLOSED. 7.1. 2 Reactor Bypass Breaker A RACKED OUT. 7 .1. 3 Reactor Bypass Breaker B RACKED OUT. Control Operator I & C
===7.1 Verify===
the following breaker line-up: 7 .1.1 Reactor Trip Breaker A CLOSED. 7.1. 2 Reactor Bypass Breaker A RACKED OUT. 7 .1. 3 Reactor Bypass Breaker B RACKED OUT. Control Operator I & C
* 001 Initial x ' .._ ' , ..
* 001 Initial x ' .._ ' , ..
* SALEM GENERATING STATION PERFORMANCE DEPARTMENT (I & C) TEST PROCEDURE NUMBER -REV. NO. DATE lPD-18.1.004 1 6/24/82 PAGE 6 OF 10 ---TITLE SOLID STATE PROTECTION SYSTEM REACTOR TRIP BREAKER & PERMISSIVE P-4 TEST -TRAIN A 8.0 Instructions: (Continued) Conne.ct the digital voltmeter as follows: 8.1.1 Reactor Trip Breaker A Cubicle TB3-l (+). 8.1. 2 Reactor Trip Breaker A Cubicle TB3-3 (-). 8.2 The DVM should read approximately 48 voe. 8.3 Have the Control Operator RACK IN and CLOSE Reactor Bypass Breaker A. 8.4 Verify on the Control Board that Reactor Bypass Breaker A is CLOSED. 8.5 The DVM should read O voe. 8.6 Have the Control bperator OPEN Reactor Trip Breaker A. 8.7 At the Control Board, verify Reactor Trip Breaker A is OPEN. I Ill C-001 Initial   
* SALEM GENERATING STATION PERFORMANCE DEPARTMENT (I & C) TEST PROCEDURE NUMBER -REV. NO. DATE lPD-18.1.004 1 6/24/82 PAGE 6 OF 10 ---TITLE SOLID STATE PROTECTION SYSTEM REACTOR TRIP BREAKER & PERMISSIVE P-4 TEST -TRAIN A 8.0 Instructions: (Continued) Conne.ct the digital voltmeter as follows: 8.1.1 Reactor Trip Breaker A Cubicle TB3-l (+). 8.1. 2 Reactor Trip Breaker A Cubicle TB3-3 (-). 8.2 The DVM should read approximately 48 voe. 8.3 Have the Control Operator RACK IN and CLOSE Reactor Bypass Breaker A. 8.4 Verify on the Control Board that Reactor Bypass Breaker A is CLOSED. 8.5 The DVM should read O voe. 8.6 Have the Control bperator OPEN Reactor Trip Breaker A. 8.7 At the Control Board, verify Reactor Trip Breaker A is OPEN. I Ill C-001 Initial   

Revision as of 17:03, 5 May 2019

Rev 1 to Solid State Protection Sys Reactor Trip Breaker & Permissive P-4 Permissive Test,Train A.
ML18087A733
Person / Time
Site: Salem  PSEG icon.png
Issue date: 12/01/1982
From:
Public Service Enterprise Group
To:
Shared Package
ML18087A720 List:
References
1PD-18.1.004, NUDOCS 8303160554
Download: ML18087A733 (12)


Text

NOTE: PRESS HARO YOU ARE MAKING FIVE (5) COPIES ADMINISTRATIVE PROCEDURE 3 CHANGE TYPE: ALL ON-THE-SPOT CHANGES TO BE CONSIDERED FOR APPLICABILITY TO BOTH UNITS. *TEMPORARY (CRANGEJ UNITZ PROCEC u RE NO. ___ , _P_t::, ___ --1 g---'-; ...... I"'"""' _0_0_4-__ _ PROCEDURE NO. __ 2 ___ P_;;D=. ---'-'

_00 __ 4-__ _ REV. NO. _ __./ __ CHANGE No._/.__ __ REV. N0. _ __,,1--_ CHANGE NO._.._/ __ PROPOSED CHANGE: C..o u e..'("' S k-e..e....

t b *... \E...-"\-e. .! T s fro c..e..&.t...c. S'-4.f'e;f" Sc deS SP( a) 4/,. 3, /. I, I "'/ REASON FOR CHANGE:

t"\.t* ACTION TAKEN FOR OTHER UNIT: 'S-4m.£' AUTHORIZATION:

    • SUPERVISOR IN CHARGE CUTY SENIOR SHIFT SUPERVISOR

-OR SHIFT SUPERVISOR

    • s1GNATURE ALSO VERIFIES THAT APPLICABILITY i:o BOTH UNITS HAS BEEN CONSIDERED.

ACCEPTABLE:

POST CHANGE-REVIEW/APPROVAL 00 D.

Rs E-:THEA-c

-!Fz°:T"t: 0; I I ,,syc (CHAIRMAN!

I 21 I I MANAGER -SALEM GENERATING STATION RETURN COMPLETED CR REJECTED FCRM TO DEPARTMENT REQUESTING CHANGE,* FOLLOW-UP TO REJECTED ON-THE-SPOT CHANGE ACTION TAKEN:

830314 ' DR ADOCK 05000272 -PDR PERFORMED BY: SIGNATURE Rll:TURN TO DEPARTMENT HEAD FOR ROUTING THROUGH POST CHANGE-REVIEW/APPROVAL CYCLE. *---.*** *-* .. *, : . : .. -.

DATE DATE FORM AP .. 3-1 REV. 9 SALEM NUCLEAR GENERATING STATION PUBLIC SERVICE ELECTRIC & GAS COMPANY ELECTRIC GENERATION DEPARTMENT PROCEDURE APPROVAL COVER SHEET' SAFETY RELATED PROCEDURE: .lPD-18 .1. 004 SOLID STATE PROTECTION SYSTEM REMARKS: REACTOR TRIP BREAKER & PERMISSIVE P-4 TEST -TRAIN A Rev. 1 -General Revision to incorporate On-The-Spot-Changes . .. EEO QA PERF. ENGR. SORC STA. SUPT. REV SUBMITTED

'APPROVED REVIEWED APPROVf¥D 1 REVIEWED APPROVED ;;*.,.,i:,.

fr-At L '(;I" fo-o V//f) 0 / ,., 'z ... . .l.-Y.H. mm "J,.( ,, &J-:it t/. //,,;.

-11n/n 7/'Z.'!o/l"Z.. , i/

1 "'rv\. R ... NlA .......... t

<i-z.--o io IJ J Ai *. '11, ..

  • t -., --* ** * -: ... ..,, **.* -r, -, ** .**** ""!'" -* ::5) x .. . , *I' ; . * *
  • SALEM GENERATING STATION PERFORMANCE DEPARTMENT (I & C) TEST PROCEDURE NUMBER -lPD-18 .1. 004 REV.NO.

DATE PAGE 1 OF 10 TITLE SOLID STATE PROTECTION SYSTEM REACTOR TRIP' BREAKE:R & PERMISSIVE p*-4 TEST -TRAIN A 1.0 Purpose 1.1 To verify the operability of the Reactor Trip Breakers to satisfy requirements of the Technical Specifications . . 1.2 To verify the operability of the Reactor Trip Breaker/ Reactor Bypass Breaker P-4 permissive switches.

1. 3 To satisfy the. recommendations o*f Westinghouse Letter PSE-80-14.

2.0 References 2.1 Solid State Protection System Manual 2.2 Westinghouse Letter PSE-80-14 (2/22/80) 2.3 Wiring Diagrams -203688, 222885, 224305, 203646 2.4 Technical Specifications 3.0 Precautions 3.1 Insure that all required safety precautions and tagging procedures have *been complied with as stated in the Performance Department Manual . I Ill C

  • 001 -**.
....... -**-*** ........
  • -* --., ....

-* *:-** .. ,,., ...... ,. ,._,. . ' ..... . -*-* -;

...

  • SALEM GENERATING STATION PERFORMANCE DEPARTMENT (I & C) . TEST PROCEDURE NUMBER -REV. NO. DATE PAGE lPD-18.1.004 l 6/24/82 2 OF 12 ---TITLE SOLID STATE PROTECTION SYSTEM REACTOR TRIP BREAKER & PERMISSIVE P-4 TEST -TRAIN A 4.0 Limitations and Actions 4.1 If, at any time during the performance of this test, there is any reason to suspect that the test equipment being used may not be performing properly, a comparison check shall be performed with *a similar device or the device shall be checked for calibration against a standard.

This shall be done prior to taking any other corrective action. 4.2 If, during the performance of this test, the "As Found" data does not meet the requirements of the specified accuracy, the*Job Supervisor shall be notified immediately and PD-14.1.001 shall be performed.

4.3 If, during the performance of this procedure, the required status indication cannot be obtained, the Job Supervisor shall be notified immediately.

Exceptions to the required indication, due to plant connitions at the time of the test, may be made by the Job Supervisor.

Any exceptions of this nature must be indicated and explained in Section 10.0 of this procedure

  • I Iii C -001 x .... -t' * .. SALEM GENERATING STATION PERFORMANCE DEPARTMENT (I & C) TEST PROCEDURE TITLE SOLID STATE PROTECTION SYSTEM NUMBER -lPD-18. 1. 004 REV. NO. 1 --------0 ATE 6/24/82 PAGE 3 OF 12 ------REACTOR TRIP BREAKER & PERMISSIVE P-4 TEST -TRAIN A 5.0 Test Equipment DEVICE. NAME PD. NO. RECAL. DATE Fluke DVM ** I & C -001 x . : f' , . * **
  • SALEM GENERATING STATION NUMBER -REV. NO. DATE lPD-18 .1. 004 . PERFORMANCE DEPARTMENT (I & C) TEST PROCEDURE 1 6/24/82 PAGE ___.4.._,__

OF 10 -TITLE SOLID STATE PROTECTION SYSTEM REACTOR TRIP BREAKER & PEEMISSIYE P-4 TEST*-TRAIN A 6.0 Prerequisites 6.1 The individual assigned to perform *this procedure is qualified to do so in accordance with the Solid State Protection System Qualification Card. Supervisor 6.2 The Senior Shift Supervisor/Shift Supervisor has granted permission to perform this procedure.

Senior Shift Supervisor/Shift Supervisor Date/Time 6.3 Tne Control Operator.is aware of all the alarms and indications that will be affected by the performance of this procedure.

Control Operator I & C -001 x . : .* ,, ... SALEM GENERATING STATION PERFORMANCE DEPARTMENT (I & C) TEST PROCEDURE NUMBER -REV. NO. DATE lPD-18.1.004 1 6/24/82 PAGE 5 OF 10 TITLE SOLID STATE PROTECTION SYSTEM REACTOR TRIP BREAKER & PERMISSIVE P-4 TEST -TRAIN A 7.0 System Line-Up: The following conditions must be established and/or verified by the Control Operator.

7.1 Verify the following breaker line-up: 7 .1.1 Reactor Trip Breaker A CLOSED. 7.1. 2 Reactor Bypass Breaker A RACKED OUT. 7 .1. 3 Reactor Bypass Breaker B RACKED OUT. Control Operator I & C

  • 001 Initial x ' .._ ' , ..
  • SALEM GENERATING STATION PERFORMANCE DEPARTMENT (I & C) TEST PROCEDURE NUMBER -REV. NO. DATE lPD-18.1.004 1 6/24/82 PAGE 6 OF 10 ---TITLE SOLID STATE PROTECTION SYSTEM REACTOR TRIP BREAKER & PERMISSIVE P-4 TEST -TRAIN A 8.0 Instructions: (Continued) Conne.ct the digital voltmeter as follows: 8.1.1 Reactor Trip Breaker A Cubicle TB3-l (+). 8.1. 2 Reactor Trip Breaker A Cubicle TB3-3 (-). 8.2 The DVM should read approximately 48 voe. 8.3 Have the Control Operator RACK IN and CLOSE Reactor Bypass Breaker A. 8.4 Verify on the Control Board that Reactor Bypass Breaker A is CLOSED. 8.5 The DVM should read O voe. 8.6 Have the Control bperator OPEN Reactor Trip Breaker A. 8.7 At the Control Board, verify Reactor Trip Breaker A is OPEN. I Ill C-001 Initial

. x .. ,. ? *, . *

  • SALEM GENERATING STATION PERFORMANCE DEPARTMENT (I & C) TEST PROCEDURE NUMBER -REV. NO. DATE lPD-18.1.

004 1 6/24/82 PAGE 7 OF 10 ------TITLE SOLID STATE PROTECTION SYSTEM REACTOR TRIP BREAKER & PERMISSIVE P-4 TEST -TRAIN A 8.0 Instructions: (Continued) 8.8 Connect*the digital voltmeter as follows: . 8.8.l Reactor Trip Breaker A Cubicle TB3-3 (+). 8.8.2 Reactor Bypass Breaker A Cubicle TB6-8 (-). 8.9 The DVM should read approximately 48 VDC

  • 8.10 Have the Control Operator CLOSE Reactor Trip Breaker A. 8.11 The DVM should read O VDC. 8 .12 Verifyb.:-On the Control Board, Reactor Trip Breaker A is CLOSED. 8.13 Have the Control Operator OPEN Reactor Bypass Breaker A. 8.14 Connect the digital voltmeter as follows: . 8.14.1 Reactor Trip Breaker A Cubicle TB3-l (+)
  • 8.14.2 Reactor Trip Breaker A Cubicle TB3-3 (-)°. Initial X .: r ., ... *
  • SALEM GENERATING STATION PERFORMANCE DEPARTMENT (I & C) TEST PROCEDURE NUMBER -REV. NO. lPD-18. l. 004 l DATE 6/24/82 PAGE 8 OF 10 TITLE SOLID STATE PROTECTION SYSTEM REACTOR TRIP BREAKER & PERMISSIVE P-4 TEST -TRAIN A 8.0 Instructions: (Continued) 8.15 The DVM should read approximately 48 VDC. 8.16 Have the Control Operator RACK OUT Reactor Bypass Breaker A. 8.17 The DVM should read approximately 48 VDC
  • 8.18 Disconnect the DVM. -. 8.19 If the Shift Supervisor wants the Safety Injection Block reinstalled for this train, jumper term.inals 2 and 6 on TDl and have the Control Operator depress the S.I. Reset for this train. Senior Shift Supervisor/Shift Supervisor 8.20 If necessary, remove the jumper placed in step 8.19. I & C -001 . -*--*-*-*-*

... ----*------

... *-*** ...... *-* -*** *-Initial x .... >-SALEM GENERATING STATION NUMBER -lPD-18 .1. 004 * . PERFORMANCE DEPARTMENT (I & C) REV.NO. _l ______ _ DATE 6/24/82 TEST PROCEDURE PAGE 9 OF 10 ---TITLE SOLID STATE PROTECTION SYSTEM REACTOR TRIP BREAKER & PERMISSIVE P-4 TEST --TRAIN A . 9.0 System Return To Normal:

  • I & C -001 The following conditions must be established and/or verified by the Control Operator.

9.1 None Required * :-*-'

x_ > ,. _,., ,r .

  • NUMBER -REV. NO. DATE lPD-18 .1. 004 1 6/24/82 SALEM GENERATING STATION PERFORMANCE DEPARTMENT (I & C) TEST PROCEDURE PAGE 10 OF 10 TITLE SOLID STATE PROTECTION SYSTEM REACTOR TRIP BREAKER & PERMISSIVE P-4 TEST -TRAIN A 10.0 Remarks: I .0. # w .o. # 11.0 Completion 11.1 Completed By: Technician Date 11.2 Approved By: Supervisor Date
  • I & C -001 -* .. -.. , .... , . ..--.......

.........

--..--........ --**-----*-

..

Time Time