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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20216G1351999-09-23023 September 1999 Rev 5 to Chapter 12 of Zion Annex Odcm ML20209F8321999-06-30030 June 1999 Rev 4,Chapter 12 of ODCM for Zion Annex ML20211C3311999-04-30030 April 1999 Rev 2.0 to Generic ODCM for Dresden,Quad Cities,Zion, Lasalle,Byron & Braidwood ML20205Q8801999-04-13013 April 1999 Proposed Tech Specs Page 5-9,replacing Operational TSs with Permanently Defueled TSs ML20154E3441998-10-0202 October 1998 Proposed Tech Specs Pages Re Amends to Licenses DPR-39 & DPR-48,eliminating License Conditions No Longer Applicable & Replacing Existing Operational Custom TS with Permanently Defueled TS ML18068A7121998-07-31031 July 1998 Rev 3 to Chapter 12 of Zion Station Odcm. 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[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20216G1351999-09-23023 September 1999 Rev 5 to Chapter 12 of Zion Annex Odcm ML20209F8321999-06-30030 June 1999 Rev 4,Chapter 12 of ODCM for Zion Annex ML20211C3311999-04-30030 April 1999 Rev 2.0 to Generic ODCM for Dresden,Quad Cities,Zion, Lasalle,Byron & Braidwood ML18068A7121998-07-31031 July 1998 Rev 3 to Chapter 12 of Zion Station Odcm. ML20217N9661998-03-31031 March 1998 Revs to ODCM for Zion Station,Including Rev 2 to Chapters 10 & 12 ML20216G8981998-03-16016 March 1998 Certified Fuel Handler Training & Retraining Program ML20216H9041997-10-31031 October 1997 Revs to OCDM for Zion Station,Including Rev 1.9 to Chapter 10,rev 1.1 to Chapter 11,rev 1.9 to Chapter 12 & Rev 1.1 to App F ML20212B4421997-10-22022 October 1997 Rev 3 to Zion Nuclear Station Recovery Plan ML20212B4471997-10-22022 October 1997 Rev 3 to Zion Nuclear Station Recovery Program,Scope Mgt Guideline ML20212B4601997-10-22022 October 1997 Rev 3 to Zion Nuclear Station Recovery Program,Sys Readiness Review ML20212B4761997-10-22022 October 1997 Rev 3 to Zion Nuclear Station Recovery Program,Dept Start- Up Readiness Assessment Guideline ML20211B4831997-09-0505 September 1997 Restart Action Plan ML20140C4151997-06-0505 June 1997 Rev 1 to Zion Nuclear Station Recovery Plan ML20137B4691997-01-31031 January 1997 Rev 1.9 to Chapter 10, Zion Annex Index & Rev 1.8 to Chapter 12, Radioactive Effluent Technical Stds ML20216E6041997-01-31031 January 1997 Amend 4 to Zion Station Fire Protection Rept ML20134H4591996-10-31031 October 1996 Rev 1.8 to Chapter 10 Odcm,Zion Annex Index ML20129E5621996-09-30030 September 1996 Rev 1.1 to Chapter 11 to Odcm,Zion Annex Index ML20129J4891995-10-0404 October 1995 On-Site Review for ODCM Revision ML20058E8751993-09-0303 September 1993 Revised AOP-6.3, Loss of RHR Shutdown Cooling ML20056H0281993-08-20020 August 1993 Errata to Chapter 12 to ODCM, Including Revised Table 12.2-1,12.2-3 & 12.5-1 ML20056G8131993-06-30030 June 1993 Pump & Valve Inservice Testing Plan for Zion Nuclear Generating Station Units 1 & 2 ML20058E8351993-06-10010 June 1993 Revised AOP-7.4, Control Room Inaccessibility ML20044H1091993-06-0202 June 1993 Rev 04/93 to, Second 10-Yr Interval Pump & Valve Inservice Testing Plan for Zion Nuclear Generating Station,Units 1 & 2 ML20035B8291993-02-28028 February 1993 Rev Oj to Odcm ML20035C9771993-02-26026 February 1993 Offsite Dose Calculation Manual Generic Sections, Rev 0.K ML20034D5441993-01-13013 January 1993 Rev 0.J to Odcm ML20127D0691992-12-30030 December 1992 Corporate Emergency Response Organization Required Reading Package 92-11 ML20245L7651989-08-0707 August 1989 Rev 0 to Offsite Dose Calculation Manual ML20235T6421987-12-31031 December 1987 Rev 11A to Offsite Dose Calculation Manual. Rev 11B to Table of Contents Also Encl ML20237F6641987-02-27027 February 1987 Revised Procedure PT-18, Control Room Charcoal Booster Fans Test ML20210U0861987-01-27027 January 1987 Procedure 91-614-04-123, Human Factors Integration of Zion Nuclear Generating Station Reg Guide 1.97 Program ML20236R9811986-08-28028 August 1986 Ae Project Plan for Evaluation of Pressurizer Safety & Relief Valve Discharge Piping Subsystem ML20205F8061986-07-25025 July 1986 Rev 0 to Procedure TSGP-47, Control Room Ventilation Sys Ductwork In-Leakage Test ML20206J6961986-06-17017 June 1986 Rev 2 to Inservice Insp & Test Program Second Interval ML20203L3551986-04-30030 April 1986 Rev 0 to Comm Ed Training Program Description for Station Control Room Engineer/Shift Technical Advisor ML20210A5651985-12-27027 December 1985 Rev 0 to Emergency Procedure ES-1.1, SI Termination ML20136G3371985-11-0808 November 1985 Suppl 4 to NUREG-0737 Suppl 1 Dcrdr Program Plan ML20207N3261985-08-12012 August 1985 Rev 0 to 2L-517 E, Steam Generator a Level Channel Electronics ML20207N3201985-08-0606 August 1985 Rev 0 to 2L-517 T, Steam Generator a Level Transmitter ML20140D0761985-06-30030 June 1985 Rev 11 to Sections 7.2 & 8.0 of Offsite Dose Calculation Manual ML20127K1211985-04-27027 April 1985 Rev 0 to Procedure Zap 6-52-5, Zion Station Equipment Technical Info Control Program ML20237F6791985-03-26026 March 1985 Revised TSS 15.6.14A, Activated Carbon Filter In-Place Leak Test ML20237F6931985-03-26026 March 1985 Revised TSS 15.6.14B, HEPA Filter Banks In-Place Leak Tests ML20237F7271985-03-26026 March 1985 Revised TSS 15.6.14C, Activated Carbon Filters Lab Analysis ML20140G0341984-04-25025 April 1984 Rev 10 to Procedure TSS 15.6 10A, Type a Containment Leak Rate Test ML20024E7771983-07-11011 July 1983 Public Version of Revised Environs Group Emergency Plan Implementing Procedures.Two Oversize Drawings Encl.Aperture Cards Available in PDR ML20024E0961983-06-10010 June 1983 Public Version of Rev 1 to Emergency Plan Implementing Procedure EPIP 550-4, Onsite Radiological Emergency Response Equipment & Receipt Form ML20024B9701983-05-17017 May 1983 Public Version of Rev 4 to Emergency Plan Implementing Procedure EPIP 420-1, Technical Support Ctr Quarterly Surveillance ML20028B9631982-11-24024 November 1982 Public Version of Revision 2 to Emergency Plan Implementing Procedure EPIP 350-1, Quick Estimate of Offsite Dose from Unplanned Release ML20027E8001982-11-10010 November 1982 Revised Pages for Inservice Testing Program for Pumps & Valves 1999-09-23
[Table view] |
Text
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2L-517 T Rev. O l
STEAM GEN A LEVEL TRANSMITTER 2L-517 T LATEST PAGE REVISIONS PAGE REVISION DATE 1
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0 AL.G 6 1983 6
0 7
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e APPROVED 'D'~C'#
DATE E#
Completion reviewed by Date Foreman Complction reviewed by
_ Date Q.C.
kDk MhCK25 8703o9 4
05000295 p
PDR 09791 I
2L-517 T Rev. 0 6
- E STEAM GEN. A LEVEL TRANSHITTER COMPUTER I.D. No.
2L**-FW*0517
1.0 PURPOSE
To establish a procedure that allows troubleshooting or calibration of level channel 2L-517 transmitter while ensuring that the protective function of the channel is performed and inadvertant reactor trips and safety injections are avoided.
2.0 REFERENCES
2.1 S&L Dwgs. No. 22E-2-4943E, AB 2.2 lectnical Specifications Sect. 4.1 2.3 IMF-MI-2 Transmitter replacement h>g @i
,p,
.d
- 2.4 IMP-MI-9 Wet / Dry transmitter calibrat4c6methEtd" IMP-MI-12 Second verificatio p k...,
2.5 dw 1..
2.6 IMP-RC-3 Determining t "j49 f transmitters in use.
NOTE For purposes f satisfying the Tech. Spec.
requirements for refueling channel calibration both this procedure and 2L-517 E must be completed.
3.0 PRERE0VISITES
3.1 The plant may be in any Mode to perform this procedure.
4.0 PRECAUTIONS
4.1 Troubleshooting or calibration may not be performed on more than one protection set (I, II, III or IV) at a time, unless the unit is in cold shutdown and the reactor trip breakers are open.
5.0 LIMITATIONS AND ACTIONS:
5.1 This procedure is for work or surveillance on the transmitter only.
For any work or surveillance on the electronics use 2L-517 E.
09791 2
2L-517 T Rev. 0 o
AUG 6 1935 5.2 Only one channel may be worked on at a. time, unless the unit is in cold shutdown and the reactor trip breakers are open.
5.3 An IDR is required if the transmitter is found out of tolerance.
5.4 If during troubleshooting a reactor protection channel alert is actuated from another protection set, the work must be terminated and all channels returned to the Normal (untripped) mode, except those tripped under the authority of AOP-9.
NOTE The loop must be intact and capable of performing it's protective function or the bistables MAY NOT be untripped.
5.5 Verify calibration date on test equipment is current.
1 5.6 Component repairs cannot be made during.s I
testing. A work request mus
, eok prior to doing repair wo
./
6.0 PROCEDURE
6.1 Record the ollowing information.
W/R #
Date 6.2 Applicable precautions and prerequisites verified.
6.3 Obtain the Shift Supervisor's permission.
(Sup. sig.)
6.4 Inform the unit NSO that work is commencing and place the loop cal in progress label on the main control board indicator for this loop.
6.5 Reactor trip breakers open.
(circle one) YES/NO NOTE If the above response is YES, proceed with Step 6.7, and N/A Step 6.6.
If the response is NO, proceed with Step 6.6.
CAUTION Inform Shift Engineer that reactor trip breakers must remain open during this surveillance if they are open when it was started.
09791 3
2L-517 T Rev. 0 AVE 6 isc5 6.6. Verify the following status lights are NOT lit on the MCB.
SG A HI LVL Turbine Trip 2LC-519A SG A HI LVL lurbine Trip 2LC-518A SG A LG-LO LVL Reactor Trip 2LC-519B SG A LO-LO LVL Reactor Trip 2LC-518B SG A L0 LVL Reactor Trip 2LC-518C A ST-FW FLO M/M Reactor Trip 2FC-510B A ST-FW FLO M/M Reactor Trip 2FC-511B 6.7 Enter computer surveillance for loop 517.
6.8 Place the following bistables in the up (tripped) position.
RACK 16 SG A HI LEVEL Turbine Trip 2BS-517A SG A LO-LO LEVEL Reactor Trip 2BS-517B SG A LO LEVEL Reactor Trip 2BS-517C 6.9 Verify the following status lights are LIT on the MCB.
SG A HI LEVEL Turbine Trip 2LC-517A SG A LO-LO LEVEL Reactor Trip 2LC-517B SG A LO LEVEL Reactor Trip 2LC-517C 6.10 Valve out transmitter 2LT-517.
a.
Shut high side isolation valve.
b.
Open equalizer valve.
c.
Shut low side isolation valve.
,63. q&
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7 k.-
09791 4
~
2L-517 T Rev. 0 AUG 6 ;3g3 6.11 1roubleshoot, repair, or calibrate the transmitter per the following calibration data.
Transmitter:
2LT-517 Location:
2RM26 728 CONTAINMENT Range:
4.5-113.1"W.C.-4-20MA Serial No.:
6904A4343A93 Manufacturer:
FISCHER-PORTER Check Point:
2TP-517-1 Remarks: SAFE 1Y RELATED--ENVIRONMENTALLY QUALIFIED Refer to IMP-MI-2 for transmitter replacement.
IMP-MI-9 wet / dry transmitter calibration method.
IMP-MI-12 second verification.
IMP-RC-3 static shift of transmitters in use.
Required output has been zero shifted 0 MV to allow for a static shift of 0 MV at operating pressure.
Values in the lef t hand column in parenthesis are reference values without any static shift correction. This data is for REFERENCE ONLY, and is not to be used for calibration.
NOTE To calibrate the transmitter, do not remove tubing.
Use the test tap to inject signals.
(REF.)
RE0VIRE0 AS FOUND AS LEFT OUT IN OUT INC DEC INC DEC VOC "W.C.
/ VOC VOC / VOC VOC / VDC (0.982) 140 /0.982
/
_ AN
- gm (2.01 3) 112 /2.013
/
/
f5 "
p (3.007) 8 07
/
/. ; '. M (4.0dOh 58 /4.002
/
SW
.nphp' /
31 /4.996
- .t 3 T..' A V'i s
/
(4.99 &
- _. '.,.. e ;G ??NY
...> g.
s..i y
%[;
s gQ&
s l
09791 5
2L-517 T Rev. 0 f.U G 6 '935 6.12 Valve in transmitter 2LT-517 per the following.
1.
Sensing line tubing in place.
2.
Test connection isolation valves shut 3.
Test connections capped or plugged.
4.
Open high side isolation valve.
5.
Shut equalizer valve.
6.
Open low side isolation valve.
NOTE 2LT-517 transmitter must be fully operational before continuing with this procedure to exit this loop.
6.13 Place the following bistables in the down (normal) position.
RACK 16 SG A HI LVL Turbine Trip 2B g
SG A LO-LO LVL Reactor Tripe M 2B ss SG A LO LVL Rea.gter"Tripli)'Q B
?,g g.;Q CAU
, ?x f'.'.
m e
tals' (hi working properly by n f push button.
6.14 Re he condition of status lights 2LC-517A, 2LC-5178, 2LC-517C.
If S/G A narrow range level is between 25% and 70% and all three lights are NOT lit, this constitutes second verification for
-I-2BS-517A, 2BS-5178, and 2BS-517C. Push the lan'p test button to prove lights.
2LC-517A LIT /NOT (circle one) 2LC-5178 LIT /NOT (circle one) 2LC-517C LIT /NOT (circle one) 6.15 Record S/G A level indicator 2LI-517, 2LI-518 and 2LI-519 reading on the MCB.
If S/G A level indication is in the narrow range and this is within the PT-0 App. L channel check tolerance of 2LI-517, this constitutes second verification of the transmitter.
If S/G level indication is not in narrow range, N/A this step.
2LI-517 2LI-518 2LI-519 6.16 S/G A narrow range level between 25% and 70% and all three status lights were not lit (circle one) YES/NO 09791 6
l
2L-517 T Rev. 0 AUG 6 isca NOTE If the above response is YES, proceed with Step 6.18, and N/A Step 6.17.
If the response is NO, proceed with Step 6.17.
6.17 Perform second verification per the following.
Verification must be performed by a second person, apart in time from the initial restoration of the equipment, a.
Verify the following bistables in the down (normal) position.
RACK 16 SG A HI LEVEL 2BS-517A SG A LO-LO LEVEL 2BS-517B SG A L0 LEVEL 2BS-517C 6.18 Transmitter is being calibrated for refueling surveillance during cold shutdown.
(circle one) YES/NO NOTE If the above response is NO, proceed with Step 6.19. If the response is YES, proceed with Step 6.21 and N/A steps 6.19 and 20. Second ve ficationofthistransmitterwillhp.,9erf4thkd the end or the outage us$^ r4MP-RI-12.'
g, e l'?
U 6.19 S/G A le a
ntthe narro e and Step 6.1 he-wi toTerance of each othe (circle one) YES/NO NOTE If the above response is NO, proceed with Step 6.20.
If the response is YES, proceed with Step 6.21 and N/A Step 6.20.
6.20 Perform second verification of the following items.
(Apart in time from the initial restoration to it's normal position and by a different person than who did the repositioning) a.
Valving of 2LT-517 1.
Sensing line tubing in place.
2.
Test connection isolation valves shut 3.
lest connections capped or plugged.
4.
Open high side isolation valve.
5.
Shut equa lizer valve.
6.
Open low side isolation valve.
09791 7
L 2L-517 T Rev. O AUG 6 1985 6.21 Exit computer IM surveillance for loop 517.
6.22 Notify Shift Supervisor and NSO that work on the channel is complete, and remove the loop cal in progress label and return it to the foreman.
6.23 Record test and r.1easurement equipment used and what it was 3 point checked against.
T&M Equio. used 3PT. CHECKED 6.24 Calibration completed by:
q
/
e 9. 9
.:n TechniciarL., r,e % D'at'e' pe WOO
/
{VW,6hnician Date p..
7.0 ACCEPTANCE CRITERIA:
7.1 The overall loop tolerance for this loop is 2.0%.
Individual component tolerances are stated in the Zion Station Instrument Tolerance Requirements, App. D of the ZIAP.
7.2 Record IDR #'s for any components which were found out
.of tolerance. N/A if none were issued.
IDR f's 7.3 The foreman will evaluate the algebraic sunnation of the "as found" component errors from the sensor to the final trip devices.
If the overall loop tolerance was exceeded a DVR shall be initiated by the foreman.
DVR REQUIRED
/
yes no 09791 8
.