ML13309B252
| ML13309B252 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 04/19/1983 |
| From: | Baskin K Southern California Edison Co |
| To: | Knighton G Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML13309B253 | List: |
| References | |
| NUDOCS 8304210315 | |
| Download: ML13309B252 (31) | |
Text
REGULATURY i RMATION DISTRIB6UTION SYSS (RIDS)
ACCESSION NOR:8304210315 DC.DATE: 83/04/19 NOTARIZED: NO DOCKET 4 FACIL:50-361 San Onotre inuclear Station, Unit 2, Southern Californ 05000361 50-362 San Onofre Nuclear Station, Unit 3, Southern Californ 05000362 AUIH. NAME AUTHUR AFFILIATION bASKINK.P.
Southern California Edison Co.
RECIP.NAME RECIPIENT AFFILIATIO 4 KNIGHTUNG.W.
Licensing branch 3 SubJECT: Forwards addl documentation & info packages provideo to A Chaffee on 630329 & 0415 re GE lype AK-2-25 reactor trip breakers (RTB),per d30317 & 21 commitments. C Moody 830415 ltr transmitting toTu surveillance procedures encl.
DISTRIBUTIUN CuDE: 8001S COPIES RECEIvED:LTR L_ ENCL SIZE:
TiTLE: Licensing Submittal: HSAR/FSAR AmOts & Relateo Correspondence NUTES:J hanchett icy POR Documents. ELD Chandler icy.
U500361 NRR Scaletti icy.
J Hanchett icy POR Documents. ELD Chancler icy.
05000362 RECIPIENT COPIES RECIPIENT COPIES I0 CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL NRk/DL/ADL 1
0 NRR LB3 LA 1
0 ROODH.
01 1
0 INTERNAL: ELD/h5D2 1
IE FILE 1
IE/OLPER/EPB 3o 5
IE/DEPER/IR6 35 1
IE/DEQA/t4AB3 21 1
NRR/DE/AEAB 1
NRK/DE/CEB 11 1
NRR/DE/EHE8 1
NRr/0E/EU8 13 2
NRR/DE/GB 28 2
NRKN/UE/HGLEib 30 1
NRR/DE/MEB 18 1
- NRr1/UE/MTEb 17 1
NRR/DE/SAb 24 1
NRk/UE/SLGE8 25 2
NRR/DHFS/HFE840 1
NR'N/HFS/LG6, 32 1
NRR/DL/SSPB I
NR1/USI/AEb 20 1
NRR/DSIOASB
.1 NRR/uSI/CPo l
NRR/DSI/CSB 09 1
NRrk/0SI/ICSB lo 1
NRR/DSI/MIETb 12 1
NRk/OSI/PSb 19 22 1
NRh/031/R,5; 23 15 04 1
1 RGN5 3
RM/DDAMI/MIb 1
0 EXTERNAL: ACRS 41 BNL(AMDTS UNLY) 1 DMol/)SS (AMiDTS) p FEMA-REP DIV 39 1
0 LPUR 03 1
1 NRC PUR 02 1
1 iSIC 05 1
1 NTIS 1
1 NOTES:
3 3
TUIAL
[jUMBE UF CuPIE5 iREu'UIRLD; LTTR 57 ENCL ifY=
Southern California Edison Company P. 0. BOX 800 2244 WALNUT GROVE AVENUE ROSEMEAD. CALIFORNIA 91770 K. P. BASKIN TELEPHONE MANAGER OF NUCLEAR ENGINEERING, (213) 572-1401 SAFETY, AND LICENSING April 19, 1983 Director, Office of Nuclear Reactor Regulation Attention: Mr. George W. Knighton, Branch Chief Licensing Branch No. 3 U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Gentlemen:
Subject:
Docket Nos. 50-361 and 50-362 San Onofre Nuclear Generating Station Units 2 and 3 SCE's letters of March 17 and 21, 1983 provided you with.copies of ten documentation and information packages that were transmitted to the NRC Resident Inspector (Mr. A. E. Chaffee) from March 13 to 18, 1983 relative to the March 1 and 3, 1983 surveillance testing of the General Electric Type AK-2-25 reactor trip breakers (RTB's) installed at San Onofre Units 2 and 3.
The letters also indicated that SCE would continue to provide you with copies of all additional information relative to the San Onofre Units 2 and 3 RTB's as it -is developed and transmitted to Mr. Chaffee.
Consistent with this commitment, enclosed please find copies of three additional documentation and information packages which were provided to Mr. Chaffee on March 29, 1983 and April 15, 1983. SCE will continue to provide you with copies of all additional information which will be developed and transmitted to Mr. Chaffee relative to the RTB's for San Onofre Units 2 and 3.
If you have any questions or comments, please let me know.
Very truly yours, Enclosure cc:
Mr. J. B. Martin, Regional Administrator U.S. Nuclear Regulatory Commission, Region V Mr. H. Rood, Project Manager (Open by addressee only - 2 sets) 8304210315 830419 PDR ADOCK 05000361 P
April 15, 1983 MR.
H. ROOD
SUBJECT:
San Onofre Nuclear Generating Station, Units 2&3 Reactor Trip Breaker Surveillance Procedures Attached per your request are copies of the Reactor Trip Breaker (RTB) Surveillance Procedures discussed at our meeting with you on April 12, 1983:
- 1. S023-II-11.161, Revision 2, Surveillance Requirements.
Reactor Breakers Undervoltage and Shunt Trip Device Circuit Test, performs a functional check of the under voltage and shunt trip circuits for the RTB's.
- 2. S023-II-11.162, Revision 0, Reactor Breaker Response Time Testing, verifies the shunt and undervoltage tripping devices are able to separately cause the breaker to trip within a specified.time.
Since the original surveillance procedure, S023-II-11.161, is now redundant to the response time procedure, S023-II-11.162, SCE may elect in the future to combine these procedures.
A formal transmittal of these procedures to the NRC will be provided next week.
/ IAA~
W. C. MOODY Deputy Station Manager MPShort:mls Attachments cc:
A. Chaffee, NRC Resident bcc:
M. P. Short M. Price o F. Nandy
FEREJcE S0123-VI-1.0 ENCODE: ACIOAC
$0123 Vi-1.1 o_
TEMPORARY CHANGE NOTICE
- -*i*ot O T r n thS-rfed m fifdmPAGE 1 OF 3
/ cnice!
Specification Woltion if root proceed within Me stored time limtsP E
No. S_0_2_3_-_II
_1_1_.161Reision No.
2 TCN No._
'rocedureTitle SURV.
REQ.
REACTOR BREAKERS UNDERVOLTAGE AND SHUNT TRIP DEVICE CIR.
TEST rocdureAuthor R.L.
CLIFT PAX 5 9 - 14 4 (If known. Wrier)
PAX
- 1.
The following change shelf be in effect Aiach a copy of the effected page(s).if app!icable SEE THE ATTACHED SHEETS
-2.
Reason PER R.N. SANTOSUOSSO LETTER OF 23 MARCH 83 TO B. KATZ TO ANSWER NRC QUESTIONS, COMMENTS AND RECOMMENDATIONS.
cDat c g naied
- 4.
Issua.nce Da:e
,(For CDV Use OnY Dorss chang aflen FSAR o! Tect. Spec comYments?
Yes-No X
6 Does t*s chae-s affect the non ad:olgIcaf envoonment of any offsite area previojs-, unjdisturbed cjring sie prepeaion anc plarnt construction? Yes No...
- 7.
Is the irnenv of the origiral document altered' Yes-No X
- 8.
Is the de:u0mer! to be charged 2n Emerwncy and Abnorma! Operaing Instruction?
Yes-No X fit the a7ser to 5, 6. 7 or# is YES..& TCN ss NOT Avrhoriaed.1
- 9.
Does this change affect licensin; commitment reqjirerents as stated in the Reference Section) Yes-No X 1o.
or igirat o, l
'/e, 41-
/S3
//e6
- 11.
Is the TCN to be incorporated into next permanent revision within 60c days of issuance date?
Yes X
No*
- Onr time change only spinsi Procedastr/Srstion Order No.
rft. No
- 12.
Copy sen: to tih Nuclear Saeiv
-y G ojp 13 Signatures Re vi uied Apprw d 2
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PROCEDURE S023-II-11.161 W
REVISION 2 TCN PAGE 2 OF 3
- 1.
Change the first sentence of 6.2 to read:
Verify proper plant status and CEDM lineup with Operations personnel.
- 2. Change 6.3.1 to read:
Observe that the selected breaker is closed. Verify that the Control Room indication shows a red light and the mimic bus on the PPS panel indicates a closed breaker. Initial the Data Record, Attachment 9.4.
- 3.
Change 6.3.3 to read:
Observe that the selected breaker opens. Verify that the Control Room indication shows a green light and the mimic bus on the PPS panel indicates an open breaker. Verify the correct Alarm has been initiated.
Initial the Data Record, Attachment 9.4.
- 4.
Change 6.3.5 to read:
Verify Control Room indication shows a red lightand the mimic bus on the PPS panel indicates a closed breaker. Verify that The Alarm has been reset.
Initial the Data Record, Attachment 9.4.
- 5.
Change 6.4.1 to read:
Observe that the selected breaker is closed. Verify that the Control Room indication shows a red light and the mimic bus on the PPS panel indicates a closed breaker. Initial the Data Record, Attachment 9.4.
- 6.
Change 6.4.3 to read:
Observe that the selected breaker opens. Verify that the Control Room indication shows a green light and the mimic bus on the PPS panel indicates an open breaker. Verify that the correct Alarm has been initiated.
Initial the Data Record, Attachment 9.4.
- 7.
Change 6.4.5 to read:
Verify Control Room indic-ation shows a red light and that the mimic bus on the PPS panel indicates a closed breaker. Verify that the Alarm has been reset. Initial the Data Record, Attachment 9.4.
- 8.
Change 6.6.1 to read:
At the completion of the test, all fuses will be checked installed and the Reactor Trip Breakers and PPS system restored to "AS FOUND" or "NORMAL STATUS".
- 9.
Change 7.1 to read:
ill TCB's function per design. The two trips, Shunt and Under-voltage, independent of each other, trip the Reactor Trip Breakers.
PROCEDURE S023-II-11.161 REVISION 2 TCN PAGE 3 OF 3
- 10.
Add to Reference Section 2.0:
2.0 Procedure S023-II-11.162, Reactor Breakers Response Time Testing.
- 11.
Add Note under 6.0 to read:
If the Reactor Breaker Response Time Testing Procedure No. S023-II-11.162, is to be implemented concurrently with this procedure, the following guidelines will apply.
- 1. Complete Procedure No. S023-II-11.162.
- 2. Complete the Data Record of Procedure No. S023-II-11.161, taking the information during the first timed test of each reactor breaker using Procedure No. S023-II-11.162.
- 3. Note in the Remarks section of Procedure No. S023-II-11.161 that Procedure No. S023-1I-11.162 was completed concurrently.
SAN ONOFRE NUCLEAR GENERONG STATION INSTRUMENT AND@ST PROCEDURE S023-II-11.161 UNITS 2 AND 3 REVISION 2 PAGE 1 COMPLETE REVISION EFFECTIVE DATE FEB! 19823 CM SURVEILLANCE REQUIREMENT REACTOR BREAKERS UNDERVOLTAGE AND SHUNT TRIP DEVICE CIRCUIT TEST (18 MONTH INTERVAL)
TABLE OF CONTENTS T
SECTION PAGE 1.0 OBJECTIVE 2
2.0 REFERENCES
2 3.0 PREREQUISITES 2
4.0 PRECAUTIONS 3
5.0 CHECK-OFF/DATA SHEET(S)
.4 6.0 INSTRUCTIONS 4
7.0 ACCEPTANCE CRITERIA 6
8.0 RECORDS 6
9.0 ATTACHMENTS 6
PAGES CHANGED WITH THIS REVISION: ALL RECEIVED FEB 10 WB2 PREPARED BY: / A
//c,23 -6'Q i PROCEDURE WRITE$
DATE EDM-SITE SITE FILE lCOPY APPROVED BY: '37L0 B. KATZ DATE MANAGER, TECHNICAL 1096b/ryh
.g SAN ONOFRE NUCLEAR GENERATING STATION INSTRUMENT AND TEST PROCEDURE S023-II-11.161 UNITS 2 AND 3 REVISION 2 PAGE 2 SURVEILLANCE REQUIREMENTS REACTOR BREAKERS UNDERVOLTAGE AND SHUNT TRIP DEVICE CIRCUIT TEST (18 MONTH INTERVAL) 1.0 OBJECTIVE 1.1 To perform a functional check of the undervoltage and shunt trip circuits on TCBs 1 through 9.
1.2 To satisfy Surveillance Requirements 4.3.1.1 (18 month interval),
Table 4.3-1, item 13 for Modes 1, 2, 3, 4 and 5 of the Unit 2 and 3 Technical Specifications.
1.3 To provide data documenting system capabilities.
2.0 REFERENCES
2.1 Applicable elementary diagrams 2.2 Applicable wiring diagrams 2.3 Applicable manufacturers' diagrams and manuals 2.4 Vendor elemetary diagrams S023-944-328 through 336 2.5 Vendor wiring diagrams S023-944-340 through 344 2.6 Operating Instruction S023-0-23 2.7 Operating Instruction S023-0-13 2.8 SCE Accident and Fire Prevention ManuaT 2.9 Station Safety Program S0123-A-138 3.0 PREREQUISITES 3.1 An Equipment Control form SO(123) 562, or a Minor PM/Surveillance Request form, SO(123) 97, may need to be submitted and approved prior to commencing work using this procedure. See Operating Instructions S023-0-23 for instruction on the use of these forms.
3.2 The applicable Work Authorization per Operating Instruction S023-0-13 must be obtained from the Control Operator prior to beginning work.
SAN ON0FRE NUCLEAR GENERATING STATION INSTRUMENT AND TST PROCEDURE S023-II-11.161 UNITS 2 AND 3 REVISION 2 PAGE 3 3.0 PREREQUISITES (Continued) 3.3 Check the applicable radiation and contamination survey information BEFORE entering job area. Use this survey information to assist in maintaining your exposure ALARA.
3.4 Verify that this procedure is current by checking this revision against a controlled copy and any Temporary Change Notices.
3.5 The steps under Section 6.0 must be completed in order.
3.6 All data must be recorded during each particular step of this procedure.
3.7 These Prerequisites are to be reverified at the beginning of each new work period not to exceed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Signatures are not required for these reverifications.
3.8 Communications between the Test Technician, Operator at the CEDM control panels, and the Control Room must be established prior to the start of the test, and maintained throughout the duration of the test.
3.9 If the Unit is shut down and a'SCRAM signal is present, contact the Instrument Department and have them remove the trip by simulating a running condition at the Plant Protection Cabinets to allow operation of the Reactor Breakers.
4.0 PRECAUTIONS 4.1 In the event any unanticipated conditiois occur during testing, the technician shall immediately notify the Control Operator.
4.2 Receiving approval to begin testing does not, in any way, obviate the responsibility of the technician to determine for himself that it is prudent and safe to begin work.
4.3 In the event the test data does not meet the acceptance criteria, the Control Operator and the applicable Supervisor shall be notified immediately. Under no circumstances shall the device be returned to service without the Control Operator's approval.
4.4 Observe the Work Authorization Holders' responsibilities under Operatihg Instruction SO23-0-13.
4.5 In conducting the activities of the procedure, various levels of circuit voltages will be energized. Exercise caution and conform to the guidelines specifies in references 2.8 and 2.9 concerning maintenance activities on energized electrical circuits.
4.6 I
ecLnrician cannot start this test as scheduled or is preve-c.fd from completing this test for any reason, a TECHNICAL SPECIFICATION VIOLATION may occur. The responsible Supervisor must be notified immediately.
SAN ONOFRE NUCLEAR GENERONG STATION INSTRUMENT AND TO PROCEDURE S023-II-11.161 UNITS 2 AND 3 REVISION 2 PAGE 4 4.0 PRECAUTIONS (Continued) 4.7 ONLY ONE BREAKER AT A TIME MAY BE TRIPPED. THE BREAKEk UNDER TEST MUST BE RECLOSED AND RETURNED TO NORMAL BEFORE TESTING MAY PROCEED ON ANY OTHER REACTOR BREAKER.
4.8 The tie breaker (TCB-9) shall not be tested if only one CEDM MG set is in service.
4.9 Necessary steps shall be taken to prevent any unscheduled trips or damage to equipment.
5.0 CHECK-OFF/DATA SHEET(S) 5.1 See Attachment 9.4.
6.0 INSTRUCTIONS 6.1 Verify communications as set forth in step 3.9. Enter the verification signature on the Data Record, Attachment 9.4.
6.2 Verify plant status and CEDM system lineup. Any deviation from normal plant status and CEDM lineup will be noted in the Remarks section of the Data Record.
6.3 Undervoltage Trip Device Circuit Test CAUTION ONLY ONE BREAKER AT A TIME MAY BE TRIPPED.
=======-
THE BREAKER UNDER TEST MUST BE RECLOSED AND RETURNED TO NORMAL BEFORE TESTING MAY PROCEED ON ANY OTHER REACTOR BREAKER.
6.3.1 Observe that the selected breaker is closed and verify that the Control Room indication shows a red light.
Initial Data Record, Attachment 9.4.
6.3.2 With an insulated fuse puller, momentarily remove the 30 amp fuse as shown on Attachment 9.1.
NOTE:
The complete designation and location for each fuse is set forth on Attachment 9.2.
6.3.3 Observe that the breaker opens and verify that the Control Room indication shows a green light and that the correct Alarm has been initiated. Initial Data Record, Attachment 9.4..
6.3.4 Hay
- .rations close the breaker under test.
SAN ONCFRE NUCLEAR GENER 9ING STATION INSTRUMENT AND T PROCEDURE S023-II-11.161 UNITS 2 AND 3 REVISION 2 PAGE 5 6.0 INSTRUCTIONS (Continued),
6.3.5 Verify Control Room indication shows a red light, and that the Alarm has been reset. Initial Data Record,.4.
CAUTION ONLY ONE BREAKER AT A TIME MAY BE TRIPPED.
THE BREAKER UNDER TEST MUST BE RECLOSED AND RETURNED TO NORMAL BEFORE TESTING MAY PROCEED ON ANY OTHER REACTOR BREAKER.
6.4 Shunt Trip Device Circuit Test 6.4.1 Observe that the breaker is closed and verify that the Control Room indication shows a red light.
Initial Data Record, Attachment 9.4.
6.4.2 Momentarily place a jumper across the terminals identified in Attachment 9.2.
6.4.3 Observe that the breaker opens and verify that the Control Room indication shows a green light and that the correct Alarm has been initiated. Initial Data Record, Attachment 9.4.
6.4.4 Have Operations close the breaker under test.
6.4.5 Verify that the Control Room indication shows a red light and that the Alarm has been reset.
Initial Data Record, Attachment 9.4.
CAUTION ONLY ONE BREAKER AT A TIME MAY BE TRIPPED.
THE BREAKER UNDER TEST MUST BE RECLOSED AND RETURNED TO NORMAL BEFORE TESTING MAY PROCEED ON ANY OTHER REACTOR BREAKER.
6.5 Complete steps 6.3 and 6.4 for all Reactor Trip Breakers TCB-1 through TCB-9. Use Attachment 9.2 for terminal locations and fuse designation and location.
SAN ON0FRE NUCLEAR ANERATING STATION INSTRUMENT AND T PROCEDURE SO23-II-11.161 UNITS 2 AND 3 REVISION 2 PAGE 6 6.0 INSTRUCTIONS (Continued) 6.6 Restoration 6.6.1 At the completion of the test, all fuses-will be checked installed and the system restored to "As Found" or "Normal Status".
6.6.2 Restore all connections, switches and devices that were altered in the performance of this procedure.
6.6.3 A second qualified person shall verify the restoration (safety related equipment only). Sign verification on Data Record, Attachment 9.4.
6.6.4 Release any Work Authorization obtained for this procedure back to the Control Operator per Operating Instruction S023-0-13.
6.6.5 When applicable, complete the required portions of the Return To Service section of Equipment Control Form SO(123) 562.
7.0 ACCEPTANCE CRITERIA 7.1 All TCBs function per the applicable drawings and meet the procedure sections requirements.
8.0 RECORDS 8.1 Upon completion of this procedure the Data Record, Attachment 9.4 shall be signed by the Technician and responsible Electrical Test Supervisor. The Supervisor of Electrical Test and I&C Engineering Representative shall review and approve the test data.
8.2 A copy of the Data Record, Attachment 9.4, of this procedure will be made for retention in the Test Shop files.
8.3 Transfer the original copy of the Data Record, Attachment 9.4, to the CDM Center.
9.0 ATTACHMENTS 9.1 Elemeptry Diagram for Breaker Control (1 page) 9.2 Terminal and Fuse Designation and Location (1 page) 9.3 TCB Bus Arrangement (1 page) 9.4 Data Record (2.
1096b
SAN ONOFRE NUCLEAR GENERATING STATION INSTRUMENT AND TEST PROCEDURE S023-11-11.161 UNITS 2 AND 3 REVISION 2 PAGE 1 OF 1 ATTACHMENT 9.1 FOR UV TEST 4)E 2 FU T T-POS 1
2I FUT C C-POs A 52 TEST.. L
\\
A
-EMERGENC*
152 2
U 552 BREER CLOSING 1/SU LiiCIRCUIT 1/52 UNDERVOLTAGE 1-NEG 4iUV TRIP DEVICE' 52 52 SHUTIRI 3
4FU C DEVICE 3
4 FU T Elementary DIagram for Breaker Control
SAN ON0FRE NUCLEAR GENERATING STATION iidSTRUMENT AND TE PROCEDURE S023-II-11.161 UNITS 2 AND 3 REVISION 2 PAGE 1 OF 1 ATTACHMENT 9.2 TERMINAL AND FUSE DESIGNATION AND LOCATION UNDERVOLTAGE SHUNT TEST LOCATION TEST BREAKER FUSE NO.
JUMPER TERMINALS TOP TCB-1 FU1T (POS)
OTB2-3 to OTB2-4 SECT. 1 REAR-RIGHT TOP TCB-2 FU2T (POS)
OTB11-3 to OTB11-4 SECT. 2 REAR-RIGHT TOP TCB-3 FU3T (POS)
OTB23-3 to OTB23-4 SECT. 4 REAR-RIGHT TOP TCB-4 FU4T (POS)
OTB32-3 to OTB32-4 SECT. 5 REAR-RIGHT TCB-5 FUST (POS)
OTB2-9 to OTB2-10 SECT. 1 REAR-RIGHT TOP TCB-6 FU6T (POS)
OTB11-9 to OTBIl-10 SECT. 2 REAR-RIGHT TOP TCB-7 FU7T (POS)
OTB23-9 to OTB23-10 SECT. 4 REAR-RIGHT TOP TCB-8 FU8T (POS)
OTB32-9 to OTB32-10 SECT. 5 REAR-RIGHT TOP TQB-9 FU9T -(.PDS)
SECT. 3 REAR-RIGHT TRIP PB ON DOOR TCB-9 BC3-to BC4 SECT.3 FRONT
SAN ONOFRE NUCLEAR GENERANG STATION INSTRIUMT AND S T PROCEDURE S023-II-11.161 UNITS 2 AND 3 REVISION 2 PAGE 1 OF 1 ATTACHMENT 9.3 TCB BUS ARRANGEMENT G SET #1 MG SET #2 HOT GEN GEN MOT MCB-1 MCB-2 SYNCH CIRCUIT.
0TRIPJ TCB-9 TCB-2 TCB-6 TCB-3 TCB-7 TCB-1 TCB-5 TCB-4 TCB-8.
CEDM POWER SUPPLY ClOM POWER SUPPLY
SAN ONOFRE NUCLEAR GENERARING STATION INSTRUMENT AND 1 PROCEDURE S023-II-11.161 UNITS 2 AND 3 REVISION 2 PAGE 1 OF 2 ATTACHMENT 9.4 REACTOR BREAKERS UNDERVOLTAGE AND SHUNT TRIP DEVICE CIRCUIT TEST PMO NUMBER DATA RECORD UNIT Test Shop File No..
6.1 Communications verified, (prerequisite).
/
Technician Date 6.2 Plant status and CEDM system lineup verified, (prerequisite).
Technician Date UNDER VOLTAGE TRIP DEVICE Reactor Closed Open Alarm Breaker Alarm Breaker Indication Trip Indication In Closed Reset TCB-1 TCB-2 TCB-3 TCB-4 TCB-5 TCB-6 TCB-7 TCB-8 TCB-9
SAN ONOFRE NUCLEAR GENERA NG STATION INSTRUMENT AND It PROCEDURE 5023-II-11.161 UNITS 2 AND 3 REVISION 2 PAGE 2 OF 2 ATTACHMENT 9.4 SHUNT TRIP DEVICE Reactor Closed Open Alarm Breaker Alarn Breaker Indication Trip Indication In Closed Reset TCB-1 TCB-2 TCB-3 TCB-4 TCB-5 TCB-6 TCB-7 TCB-8 TCB-9 6.6 Restoration 6.6.1 Restoration Completed Technician
/
Date Secord Qualified Person / Date 6.8 REMARKS TECHNICIAN(S)
-DATE DATE DATE _
DATE ELECTRICAL TEST SUPERVISOR DATE SViSOR OF ELECTRICAL TEST DATE RING REPRESENTiTIV:
JATE
REFEEICE 5013-Vll.OENCODE:
ACIOAC REFERENTE:
50123-Y1-1.0 50 S012.3-I-1. I V
(when form filled out)
TEMPORARY CHANGE NOTICE NOTE:
TECHNICAL SPECIFICATION VIOLATION IF NOT PROCESSED WITHIN THE STATED TIME LIMITS.
Procedure No. S023-II-11.162 Revision No.
0 TeN No._
Procedure Title R TINE TESTING Procedure Author R.
L.
CLIFT PAx 59144(if known, writer)
PAX
- 1.
The following change shall be in effect:
[Attach a copy of the effected page(s). if applicable)
SEE ATTACHED
- 2. Reason:
TO CLARIFY INTENT OF PROCEDURE
- 3. (a) Is this change a result of a facility design change?
(PFC.
NCR. or Temporary Modification, etc.)
YES No If yes, provide the facility design change identifier (b) Completion of the facility design change has been verified.
(Need only oe completed if (a) is YES)
YES-NO (if the answer to 3. (b) is NO, a TCN is NOT authorized.
- 4. Date originated _4__ 3
- 5. Issuance date 1For CUM Use Only)
- 6. Does this change affect TSAR or Tech. Spec. comitments? YES_
NO__
- 7. Does this change affect the nonradiological environment of any offsite area previously undisturbed during site preparation and plant construction? YES ____
- 8. Is the intent of the original document altered? YESN
- 9. Is the document to be changed an Emergency and Abnoraal Operating Instruction?
YES_
N_
(If the answer to 6, 7, 8 or 9 is YES. a TCN is NOT authorized)
- 10. Does this change aff t licensing comitment requirements as stated in the Reference Section?
YES No I. Originator (e
i-tafieklJ4PA-7 (Signature) rT/-DaeT ime
- 12. Is the TCN to be incorporated into next permanent revision within 60 days of issuance date?
YES _L.-"-**0M*
- One time change only against Procedure/Station Order No.
Rev. No.
- 13. Copy sent to the Nuclear Safety Group Dat CDM4 Signature Date
- 14. Signatures Required:
Approved by:
(at least one (1) SRD)
Final approval by:FILE Copy M n izaft IunctfoRal StatiEn ManagerC 8304210320 830419 PDR ADOCK 05000361 ate -
.st bo within 4 dyPR 14 1983 PDR APR_14_1983 roval must be by two members of the plant management staff at least oe of whom holds a unit affected.
(For TN proval, members of the plant management staff are defined as any Supervisor..including the lev of foreman. exercising responsibility in the specific area and unit addressed by the change).
SCE S0(123) 110 REV. 4 4/8/83
PROCEDURE 5023-I-11.162 REVISI 0
TCN I PAGE 2 OF 3
- 1.
Change the first sentence.of 4.6 to read:
WITH THE UNIT IN SERVICE ONLY ONE BREAKER AT A TIME MAY BE TRIPPED.
- 2.
Change the first sentence of CAUTION after 6.4 to read:
WITH THE UNIT IN SERVICE ONLY ONE BREAKER AT A TIME MAY BE TRIPPED.
- 3.
Change the first sentence of CAUTION after 6.4.4 to read:
WITH THE UNIT IN SERV:CE ONLY ONE BREAKER AT A TIME MAY BE TRIPPED.
- 4.
After CAUTION after 6.4 add the following:
NOTE:
Attachments 8.1 and 8.2 list convenient attachment locations.
- 5.
Change 6.4.2 to read:
Use the selected auxiliary contacts (pallets) to time opening of the breaker. Connect test leads to the appropriate terminal blocks on the rear of the switchgear.
- 6.
Change 6.5.2 to read:
Use the selected auxiliary contacts (pallets) to time opening of the breaker. Connect test leads to the appropriate terminal blocks on the rear of the switchgear.
- 7.
Change the first sentence of CAUTION after 6.5.4 to read:
WITH THE UNIT IN SERVICE ONLY ONE BREAKER AT A TIME MAY BE TRIPPED.
- 8.
Change heading on Attachment 8.2 to read:
TERMINAL LOCATIONS OF AUXILIARY CONTACTS (PALLETS).
SAN COFRE.NUCLEAR GENE ING STATION INSTRUMENT AND T PROCEDURE S023-II-11.162 UNITS 2 AND 3 REVISION 0 PAGE 1 EFFECTIVE DATE AIR 12 1983 cDRa REACTOR BREAKER RESPONSE TIME TESTING TABLE OF CONTENTS SECTION PAGE 1.0 OBJECTIVE 2
2.0 REFERENCES
2 3.0 PREREQUISITES 2
4.0 PRECAUTIONS 3
5.0 CHECK-OFF LIST(S) 4 6.0 PROCEDURE 4
6.1 Communications 4
6.2 Plant and CEDM Status 4
6.3 Acceptance Criteria 4
6.4 Response Time Testing - Undervoltage Trip Device 5
6.5 Response Time Testing - Shunt Trip Device 5
6.6 Instruction for Test 6
6.7 Restoration 6
7.0 RECORDS 6
8.0 ATTACHMENTS 7
PAGES CHANGED WITH THIS REVISION:
NEW PREPARED BY:
PROCEDURE WRTER DATE APPROVED BY:
_4__
-w3 B. KATZ DATE MANAGER, TECHNICAL 2575b/daj MW IEVCED
SAN ON0FRE NUCLEAR GEN16TING STATION INSTRUMENT AND(
T PROCEDURE S023-II-11.162 UNITS 2 AND 3 REVISION 0 PAGE 2 REACTOR BREAKER RESPONSE TIME TESTING 1.0 OBJECTIVE 1.1 To perform a response time test on each Reactor Breaker to prove that the Shunt and Undervoltage tripping devices are able to separately cause the breaker to trip within a specified time.
1.2 To provide data that will document the response time of each Reactor Breaker.
2.0 REFERENCES
2.1 Applicable elementary diagrams 2.2 Applicable wiring diagrams 2.3 Applicable manufacturers' diagrams and manuals 2.4 Vendor elementary diagrams 5023-944-328 through 336 2.5 Vendor wiring diagrams S023-944-340 through 344 2.6 Operating Instruction S023-0-23 2.7 Operating Instruction S023-0-13 2.8 SCE Accident and Fire Prevention Manual 2.9 Station Safety Program S0123-A-138 2.10 Procedure S023-II-11.161 Surv. Req. Reactor Breakers Undervoltage and Shunt Trip Device Circuit Test 3.0 PREREQUISITES 3.1 An Equipment Control Form SO(123) 562, or a Minor PM/Surveillance Request Form, SO(123) 97, may need to be submitted and approved prior to commencing work using this procedure. See Operating Instruction S023-0-23 for instructions on the use of these forms.
3.2 The applicable Work Authorization per Operating Instruction S023-0-13 must be obtained from the Control Operator prior to beginning work.
3.3 Check.the-applicable radiation and contamination survey information BEFORE~entering job area.
Use this survey information to assist in maintaining your exposure ALARA.
3.4 Verify that this procedure is current by checking this revision against a contrnllpd copy and any Temporary Change Notices.
3.5 All data
'i during each particular step of this procedure.
SAN NOFRE NUCLEAR GE16ATING STATION INSTRUMENT AND*ST PROCEDURE S023-II-11.162 UNITS 2 AND 3 REVISION 0 PAGE 3 3.0 PREREQUISITES (Continued) 3.6 These Prerequisites are to be re-verified at the beginning of each new work period not to exceed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Signatures are not required for these re-verifications.
3.7 Communications between the Test Technician, Operator at the CEDM control panels, and the Control Room must be established prior to the start of the test, and maintained throughout the duration of the test.
3.8 If the Unit is shut down and a SCRAM signal is present, contact the Instrument Department and have them remove the trip by simulating a running condition at the Plant Protection Cabinets to allow operation of the Reactor Breakers.
3.9 Test Equipment 3.9.1 Electronic Timer or Oscillograph Recorder 3.9.2 DMM (Digital Multimeter) 3.9.3 Switches, leads, hand tools, etc.
3.10 Measuring and Test Equipment (M&TE) to be used for this test shall have a current calibration history, have an accuracy better than the allowable accuracy of the device to be calibrated, and be NBS traceable.
3.11 This test will normally be performed with the breaker in the "racked in" position, but can be performed in the "In Test" position. This will keep the circuitry intact to the undervoltage coil with the diede in the coil circuit.
4.0 PRECAUTIONS 4.1 In the event any unanticipated conditions occur during testing, the technician shall immediately notify the Control Operator.
4.2 Receiving approval to begin testing does not, in any way, obviate the responsibility of the technician to determine for himself that it is prudent and safe to begin work.
4.3 In the event the test data does not meet the acceptance criteria, the Control Operator and the applicable Supervisor shall be notified immediately. Under no circumstances shall the device be returned to serviqie without the Control Operator's approval.
4.4 Observe the Work Authorization Holders' responsibilities under Operating Instruction S023-0-13.
4.5 In conducting the activities of the procedure, various levels of circuit voltages i b energized. Exercise caution and conform to the guidelines specified in References 2.8 and 2.9 concerning maintenance activities on energized electrical circuits.
SAN ONOFRE NUL"EAR GESATING STATION INSTRUMENT AN#ST PROCEDURE S023-II-11.162 UNITS 2 AND 3 REVISION 0 PAGE 4 4.0 PRECAUTIONS (Continued) 4.6 ONLY ONE BREAKER AT A TIME MAY BE TRIPPED. THE BREAKER UNDER TEST MUST BE RECLOSED AND RETURNED TO NORMAL BEFORE TESTING MAY PROCEED ON ANY OTHER REACTOR BREAKER.
4.7 The tie breaker (TCB-9) shall not be tested if only one CEDM MG set is in service.
4.8 Necessary steps shall be taken to prevent any unscheduled trips or damage to equipment.
5.0 CHECK-OFF LIST(S) 5.1 None 6.0 PROCEDURE 6.1 Verify communications as set forth in step 3.7. Enter the verification signature on the Data Record, Attachment 8.3.
6.2 Verify the proper plant status and CEDM lineup with Operations personnel.
Any deviation from normal plant status and CEDM lineup will be noted in the Remarks section of the Data Record, Attachment 8.3.
6.3 Acceptance Criteria 6.3.1 With timing leads connected to the auxiliary switch (pallets) contacts and the breaker installed in the cubicle, the maximum time response shall be 100 msec, per CE guidelines.
6.3.2 If the time is >82 msec and <100 msec, the Supervisor of I&C Electrical Engineering sEall be notified immediately for the purpose of investigating possible degradation of the tripping devices or breaker.
6.3.3 If the time is >100 msec, the breaker shall be declared inoperable and the Cognizant Supervisor and Control Operator shall be notified immediately.
NOTE:
The 82 msec time is based upon the maximum average test time that was noted during testing by SCE Apparatus Division in concert with GE.
This time includes the extra time added using the auxiliary contacts.
SAN ONOFRE NUCLEAR GE&
IATING STATION INSTRUMENT AND ST PROCEDURE 5023-11-11.162 UNITS 2 AND 3 REVISION 0 PAGE 5 6.0 PROCEDURE (Continued) 6.4 Response Time Testing -
Undervoltage Trip Device CAUTION ONLY ONE BREAKER AT A TIME MAY BE TRIPPED. THE BREAKER UNDER TEST MUST BE RECLOSED AND RETURNED TO NORMAL BEFORE TESTING MAY PROCEED ON ANY OTHER REACTOR BREAKER.
6.4.1 Set up the timing device to be able to time upon loss of the Reactor Breaker control power, and indicate the interval between the loss of power and the opening of the breaker.
6.4.2 Use the auxiliary contacts (pallets) to time opening of the breaker. Connect test leads to the terminal blocks on the rear of the switchgear per Attachment 8.2.
6.4.3 With the timing device connected, remove the power to the undervoltage circuit for the selected breaker, and time from loss of voltage to the breaker opening. Have the breaker closed and repeat the trip twice more. Record the three times on the Data Record, Attachment 8.3.
6.4.4 Return the breaker to the closed or "As Found" condition.
CAUTION ONLY ONE BREAKER AT A TIME MAY BE TRIPPED.
THE BREAKER UNDER TEST MUST BE RECLOSED AND RETURNED TO NORMAL BEFORE TESTING MAY PROCEED ON ANY OTHER REACTOR BREAKER.
6.5 Response Time Testing -
Shunt Trip Device 6.5.1 Set up the timing device to be able to time from the initiation of the signal to the shunt trip device to the breaker tripping (opening).
6.5.2 Use the auxiliary contacts (pallets) to time opening of the breaker. Connect test leads to the terminal blocks on the rear of the switchgear per Attachment 8.2.
6.5.3 Initiate a trip signal to just the shunt trip device by closing the circuit, identified in Attachment 8.1 for the selected bre:.
"; i
.. interval between initiation.
of the trip signal and the breaker.ttrjfing (opening).
Have the breaker closed and repeat the trip twice more. Record the three times on the Data Record, Attachment 8.3.
SAN ON0FRE'NUCLEAR GENING STATIG
'STRUMENT AND T PROCEDURE 5023-11-11.162 UNITS 2 AND 3 REVISION 0 PAGE 6 6.0 PROCEDURE (Continued) 6.5.4 Return the breaker to the closed or "As Found" condition.
CAUTION ONLY ONE BREAKER AT A TIME MAY BE TRIPPED.
THE BREAKER UNDER TEST MUST BE RECLOSED AND RETURNED TO NORMAL BEFORE TESTING MAY PROCEED ON ANY OTHER REACTOR BREAKER.
6.6 Complete steps 6.4 and 6.5 for all Reactor Trip Breakers TCB-1 through TCB-9. Use Attachments 8.1, 8.2 for terminal locations and fuse designation and location.
6.7 Restoration 6.7.1 Remove all test leads and test equipment.
6.7.2 At the completion of the test, all fuses will be checked installed and the Reactor Trip Breakers and PPS system restored to "As Found" or "Normal Status."
6.7.3 Restore all connections, switches and devices that were altered in the performance of this procedure.
6.7.4 A second qualified person shall verify the restoration (safety-related equipment only).
Sign verification on Data Record, Attachment 8.3.
6.7.5 Release any Work Authorization obtained for this procedure back to the Control Operator per Operating Instruction S023-0-13.
6.7.6 When applicable, complete the required portions of the Return To Service section of Equipment Control Form SO(123) 562.
7.0 RECORDS 7.1 Upon completion of this procedure, the Data Record, Attachment 9.4 shall be signed by the Technician and responsible Electrical Test Supervis6r. The'Supervisor of Electrical Test and I&C Engineering Representative shall review and approve the test data.
7.2 A copy of the Data Record, Attachment 8.3, of this procedure will be made for retention in the Test Shop files.
7.3 Transfer the original copy of the Data Record, Attachment & ?
4'+ "
CDM Center.
UNT 2NR ANCEA 3E T
STATION NT('.1r OuNOFRE n NUCLAR
!EArNu ANowST PROCEDURE 5023-II-11.162 UNITS 2 AND 3 REVISION 0 PAGE 7 8.0 ATTACHMENTS 8.1 Terminal and Fuse Designation and Location For Trips 8.2 Test Lead Connections 8.3 Reactor Breaker Response Time Test Data Record 2575b
SAN ON0FRE.NUCLEAR GENE ING STATION INSTRUMENT AND If PROCEDURE 5023-II-11.162 UNITS 2 AND 3 REVISION 0 PAGE 1 OF 1 ATTACHMENT 8.1 TERMINAL AND FUSE DESIGNATION AND LOCATION FOR TRIPS UNDERVOLTAGE SHUNT TEST LOCATION TEST BREAKER FUSE NO.
TRIP TERMINALS TOP TCB-1 FUlT (POS)
OTB2-3 to OTB2-4 SECT. 1 REAR-RIGHT TOP TCB-2 FU2T (POS)
OTB11-3 to OTB11-4 SECT. 2 REAR-RIGAT TOP TCB-3 FU3T (POS)
OTB23-3 to OTB23-4 SECT. 4 REAR-RIGHT TOP TCB-4 FU4T (POS)
OTB32-3 to OTB32-4 SECT. 5 REAR-RIGHT TCB-5 FU5T (POS)
OTB2-9 to OTB2-10 SECT. 1 REAR-RIGHT TOP TCB-6 FU6T (POS)
OTB11-9 to OTBI-10 SECT. 2 REAR-RIGHT TOP TCB-7 FU7T (POS)
OTB23-9 to OTB23-10 SECT. 4 REAR-RIGHT TOP TCB-8 FU8T (POS)
OTB32-9 to OTB32-10 SECT. 5 REAR-RIGHT TOP TCB-9 FU9T (POS)
SECT.
3 REAR-RIGHT TRIP PB ON DOOR TCB-9 BC3 to BC4 SECT. 3 FRONT
SAN ON0FRE^NUCLEAR GENERING STATION INSTRUMENT AND PROCEDURE S023-II-11.162 UNITS 2 AND 3 REVISION 0 PAGE 1 aF 1 ATTACHMENT 8.2 TEST LEAD CONNECTIONS BREAKER TERMINALS CONTACT TYPE LOCATION TOP TCB-1 OT85-9 to OTBS-10 NO(a)
SECT.
1 REAR-LEFT OTB5-11 to OTB5-12 NC(b)
TOP TCB-2 OTB14-9 to OTB14-10 NO(a)
SECT. 2 REAR-LEFT OTB14-11 to OTB14-12 NC(b)
TOP TCB-3 OTB26-9 to OTB26-10 NO(a)
SECT. 4 REAR-LEFT OTB26-11 to OTB26-12 NC(b)
TOP TCB-4 OTB35-9 to OTB35-10 NO(a)-
SECT. 5 REAR-LEFT OTB35-11 to OTB35-12 NC(b)
TOP TC85 OTB8-9 to OTB8-10 NO(a)
SECT. 1 REAR-LEFT OTB3-11 to OTB8-12 NC(b)
TOP TCB6 OTB17-9 to OTB17-10 NO(a)
SECT. 2 REAR-LEFT T17-11 to OTB17-12 NC(b)
TOP TCB7 OTB29-9 to OTB29-10 NO(a)
SECT. 4 REAR-LEFT OTB29-11 to OTB29-12 NC(b)
TOP TCB8 OTB38-9 to OTB38-10 NO(a)
SECT. 5 REAR-LEFT OTB38-11 to OTB38-12 NC(b)
TOP TCB9 OTB21-9 to OTB21-10 NOa)
SECT. 3 REAR-LEFT OTB21-11 to OTB21-12 NC(b)
SAN ONOFRE NUCLEAR GENETING STATION INSTRUMENT ANDFi PROCEDURE S023-II-11.162 UNITS 2 AND 3 REVISION 0 PAGE 1 OF 3 ATTACHMENT 8.3 REACTOR BREAKERS RESPONSE TIME TEST PMO NUMBER DATA RECORD UNIT Test Shop File No.
6.1 Communications verified, (prerequisite).
Technician Date 6.2 Plant status and CEDM system lineup verified, (prerequisite).
Technician / Dte UNDER VOLTAGE TRIP DEVICE Reactor Breaker Trip.*
Trip
- Trip
- Breaker Closed Breaker "As Found" Time 1 Time 2 Time 3 Or "As Found" TCB-1 TCB-2 TCB-3 TCB-4 TCB-5 TCB-6 TCB-7 TCB-8 TCB-9
- Time is in msec.
SAN ONOFRE NUCLEAR GENEPING STATION INSTRUMENT AND To PROCEDURE S023-II-11.52
'UNITS 2 AND 3 REVISION 0 PAGE 2 OF 3 ATTACHMENT 8.3 Test Shop File No.
SHUNT TRIP DEVICE Reactor Breaker Trip
- Trip
- Trip
- Breaker Cloed Breaker "As Found" Time I Time 2 Time 3 Or "As Foue" TCB-1 TCB-2 TCB-3 TCB-4 TCB-5 TCB-6 TCB-7 TCB-8 TCB-9
- Time is in msec.
6.6 Restoration 6.6.1 Restoration Completed Technician
/
Date Second Qualified Person
/
Date
SAN ONOFRE NUCLEAR GENERATING STATION INSTRUMENT AND TESPROCEDURE 023-11-11.162 "UNITS 2 AND 3 REVISION 0 PAGE 3 OF 3 ATTACHMENT 8.3
-DATA RECORD Measuring and Test quipment TEST SHOP FILE NUMBER Record all instruments used in this procedure I
TYPE I
I MODEL-STYLE I I SERIAL I DATE CALI.
IINSTRUMENT I MANUFACTURER NUMBER I RANGE NUMBER I ACCURACY l DUE I
I!I I
I I
I I I
I I
I Ij I
I I
II I
II I
I1 I
I II I
I I
I I
I '
I I
I I I
III I
I*II
.I Remarks:
TECHNICIAN(S)
DATE DATE ELECTRICAL TEST SUPERVISOR DATE SUPERVISOR OF ELECTRICAL TEST DATE I&C ENGINEERING REPRESENTATIVE DATE