ML20082S663
| ML20082S663 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 08/31/1991 |
| From: | Losekshort C, Robey R COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| RAR-91-35, NUDOCS 9109170234 | |
| Download: ML20082S663 (22) | |
Text
/ -
4 RAR-91-35 i
September 3, 1991 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Hashington, D.C. 20555
SUBJECT:
Quad Cities Nuclear Station Units 1 and 2 Monthly Performance Report NRC_Dochet Nos50-25L and_50-165 Enclosed for your information is the Monthly Performance Report covering the operation of Quad-Cities Nuclear Power Station, Units One and Two, during the month of August 1991.
Respectfully, COMMONHEALTN EDISON COMPANY QUAD-CITIES NUCLEAR POWER STATION b-af R. A. Robey Technical Superintendent RAR/ CAL 5/dak Enclosure cc:
A. B. Davis, Regional Administrator T. Taylor, Senior Re;1 dent Inspector
'f 9109170234 910831 PDR ADOCK 05000254
[
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PDR f
TS 14
QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT AUGUST 1991 COMMONHEALTH EDISON COMPANY AND IOHA-ILLIN0IS GAS & ELECTRIC COMPANY NRC DOCKET NOS. 50-254 AND 50-265 LICENSE NOS. DPR-29 AND
- -30 i
l TS 14
TADLE OF CONTENTS I.- Introduction II.
Summary _of Operating Experience A.-
Unit One B.
Unit Two r-III.
Plant or Procedure Changes, Tests, Experiments, and Safety Related Haintenance j
A.. Amendments to Facliity License or Technical Specifications
-l B.
Facility or Procedure Changes. Requiring NRC Approval C.-
Tests and_ Experiments Requiring NRC Approval D.
Corrective-Maintenance of Safety Related Equipment IV.
Licensee Event Reports 4
V.
Data Tabulations l
A.
_ Operating Data Report B.
Average Daily Unit Power Level 10.
Unit Shutdowns and Power Reductions
-VI.
Unique Reporting _ Requirements A.
Main Steam Relief Valve Operations B.
Control Rod Drive Scram Timing Data VII. l Refueling Information VIII. Glossary a
A TS 14
I.
INIRODUC110N Ouad-Cities Nuclear Power Station is composed of two Bolling ' dater Reactors, each with a Maximum Dependable Capacity of 769 MWe Net, located in Cordova, Illinois.
The Station is jointly owned by Commonwealth Edison Company and lowa-Illinois Gas & Electric Company.
The Nuclear Steam Supply Systems are General Electric Company Boiling Water Reactors.
The Architect / Engineer was Sargent & Lundy, Incorporated, and the primary construction contractor was United Engineers & Constructors.
The Mississippi River is the condenser cooling water source, The plant is subject to license numbers DPR-29 and DPR-30, issued October 1, 1971, and March 21, 1972, respectively; pursuant to Docket Numbers 50-254 and 50-265.
The date of initial Reactor criticalities for Units One and Two, respectively were October 18, 1971, and April 26, 1972. Commercial generation of power began on February 18, 1973 for Unit One and March 10, 1973 for unit Two.
This report was compiled by Cynthia A. Losek-Short and Debra Kelley, telephone number 309-654-2241, extensions 2938 and 2240.
TS 14
4 II.
SultiARLQf_DEEMURG EXPERIENCE A.
Unit _Qng 1
Unit One began the month of August operating on a load drop which was
.equested by Chicago Load Dispatch.
Load drops occurred on the 4th, 5th, 6th, 9th, 10th 11th, 12th, 13th, 16th, 18th, 20th, 21st, 23rd, 24th, 25th and 28th as requested by Chicago Load Dispatch.
Load drops also occurred on the 13th and 26th for LCO's due to failure of Secondary Containment Test (T.S. 3.0.A) and for exceeding 90 minute-raintenance limit on Unit 1 Diesel Generator (T.S. 3.9.E.1) respecetively.
B.
Unit _lwo j
Unit Two began the month.of August operat ig in Economic Generation Control (EGC).
The unit experienced load drops on the 15th,-22nd, 23rd,-25th, 30th and 31st as requested by Chicago load Dispatch.
Load drops also: occurred on the 13th and 26th for LCO's due to failure of Secondary Containment Test (T.S. 3.0.A) and Unit 2 Diesel _ Generator being declared inoperable (T.S. 3.9.E.1) respectively.
Unit Two began coastdown on August 20,.1991 in preparation for Unit 2 Refuel Outage, W
f k
TS 14 t
l III. El.ARI_0JLEROCEMRE_CHANGELlESIS. _EEERIMEHIX.
AND SAFETY REL61EQlMMIEMNCE A.
Amen dmentLto_Eac11LtLLkenie_or_leIhnkaLS perif3r allons Technical Specification Amendment No. 131 was issued on August 14, 1991 to Facility Operating License No. OPR-29 for Quad Cities Nuclear Power Station.
This amendemnt revises the Technical Specification to reflect the changes relative to Instrument Functional Testing and Calibration.
Technical Specification Amendemnt No. 126 was also issued August 14, 1991 to facility Operating Licnese No. OPR-30 for Quad Cities Nuclear Power Station.
This amendment also reflects the changes relative to Instrument functional Testing, Calibration, and Instrument Checks.
B.
ficj i l ty or PrQcedurf_ChangeLReRukiPglRC_ Approval There were no Facility or Procedure changes requiring NRC approval for the reporting period.
C.
Igittand_Exneriments Re_q' king _EC_Apptcy31 1
There were no Tests or Experiments requiring NRC approval for the reporting period.
D.
Corrett11elaint1nanc e_of_SafflylelatfLEaulamstni The following represents a tabular summary of the major safety related maintenance performed on Units One and Two during the reporting period.
This summary includes the following:
Hork Request Numbers, Licensee Event Report Numbers, Components, Cause of Malfunctions, Results and Effects on Safe Operation, and Action Taken to Prevent Repetition.
TS 14 1
m UNIT I MAIRTENANCE
SUMMARY
HORK_RICUI M S1 SIB EID DESCRIPTION WORK PERFORMED 094416, Q94414 0020 Repair or replace as necessary Replaced seals on doors.
Q94417, Q94413 seals for doors on secondary 094411 containment boundary.
Q94415 0020 Repair or replace seals on 1/2 As Found:
Found leaks around door seal. As trackway Inner interlock for left: Repaired door seal.
trackway inner doors.
Q72443 1700 Investigate monitor which spiked Rejacted monitor back to vendor under P.O.
downscale while being used as a
- 502204, QC-55.
replacement chassis for MSL monitor.
Q?4160 0302 Investigate alarm 0-1 on 901-5 As Found: Circuit board S.I. #794G98 suspected to panel comes up for no apparent have erratic operation. As Left:
It was decided to change the circultboard S.I. #794G98 and check reason.
wiring in junction box. Found no actual loose wires but snugged up the terminations anyway.
Replaced circuit board and performed ST 25-1.
Adjusted trips to specifications and checked it at least ten times.
Looked ok.
Work Request #Q94319 written to have original board sent back to the vendor to be refurbished.
093366 1102 Repair or replace U-l A SBLC pump As Found: Packing leaking in all three cylinders, stuffing box loose packing gland also noted the cylinder head gaskets leaking badly causing excessive leaking.
on all three cylinders. As left: Removed cylinder heads, pistons and packing from pump and found no discrepancies other than one cylinder had an unidentifiable follower in it.
Cleaned all components removed the excess boron buildup in l
pump area round stuffing boxes. Repacked the pump using glass-filled teflon follower at bottom of stuffing box, 5 rings of braided square packing with another teflon glass follower, then the t
gland. New head gaskets were installed and heads torqued to 75 ft/lb final valve.
TS 15
ILNIT 1 MAINTENANCE
SUMMARY
h0RK RgrAEST SYSTEM EID DESCRET10N HORK PERFORMED 092575 8941 Repair or replace broken seal As Found: Sealtight had been pulled loose from tight on CBLS to 8941-710 valve.
sealtight fitting and red wire had insulation broken but did not have any damage to conductor.
As Left: Replaced sealtight and taped conductor.
l l
TS 15
UNIT 2 MAINTENANCE
SUMMARY
HQE_K RE00EST SYSTEM EID DESCRIPTION HORK PERFORMED 094412 0030 Repair and replace seals on U-2 As Found:
Rubber seal toc short on hinge side of MSIV room interlock doors.
door and latch side of door on inner door and outer door. As Left: Replaced rubber in latch side and hinge side seals and adjusted seals.
Recaulked hinge side and adjusted door bottom seals sweep on inner door and outer door.
084459 0263 Repair topaz inverter removed ATHS inverter shipped to vendor for repair.
under 084443.
Vendor scrapped inverter because it was obsolete and no longer acceptable for nuclear operations.
094416 0020 Repair or replace seals on U-l As Found: Seals were damaged and sweeps need 3rd floor Reactor building replacement and adjustment. As Left:
Installed interlock doors.
new seals and new sweeps.
l l
TS 15 N
s.
1 IV.
LLCEliSLLEVIMLREPORIS The following is a tabular summary of all licensee event reports for f
Quad-Cities Units One and Two occurring during the reporting period, pursuant i
to the reportable occurrence reporting requirements as set forth in sections 6.6.B.1 and 6.6.B.2 of the' Technical Specifications.
)
UNIL1 f
Licensee Event Report _ Number Date 111]e_oL0ccuttence l
h 91-011*
04/29/91 RCIC oscillation during performance of QCOS 1300-7 RCIC manual initiation test, i
?91-011 08/13/91 Failure of Secondary containment.
i 91-014 08/07/91 SBGT Heater Locig Circtaitry mitsing, j
i UNU_2 91-09 08/17/91 Failure of Core Spay Room Orain Check Valves.
-i t
f 1
i 91-011 Report for the-Month of April has been downgraded.
[
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P i
h TS 14 i
v.
DAIAJABULallDBS The following data tabulations are presented in this report:
A.
Operating Data Report B.
Average Daily Unit Power Level C.
Unit Shutdowns and Power Reductions TS 14
t APPENDIX C
' OPERATING DATA REPORT DOCKET NO. 50-254 t
UNIT One DATE September 5, 1991
}
COMPLETED BY Cynthia Losek-Short l
309-654-2241 TElEPHONg OPERATING 8TATUS 50000 080191 744 l
52400 083191 Cross HOURS iN RePORTINO PERICO:
- 1. Rep 0RTINO PERs00:
max OEPENO. CAPACITY teneoNed; 769
" 3. CURRENTLY AUTwCRize0 POWER LEVEL (g. 2 ? 11 DESIGN ELSCTRICAL RATING (MWu.Neth N/A
- 3. POWER LEVEL TO WHICH M88TRICT80 tif ANYI (MWe> Noti:
- 4. REASONS POR R887RICTl006 (IP ANY1:
y THIS MONTM YM TO OAft CUMULATIV8
[
744.0 2267.0 133748.9_
' 5. NUMSSR OF HOURS REACTOR WA8 CRITICAL,.............
O.O o.o 3421.9_
j
- 8. REACTOR reserve SMUTOOWN MouRs...................
744.0 2140.3 129509.6
(
- 7. HOURS GENER ATOR 000 LINE. ^..................
0.0 0.0 909.2 E.- UNIT RES$MVS SMUT 00WN MOURS..................
f
- 9. GR088 THERMAL ENERGY GENERATED (MWM).......,.,,. 742244.0 482808?.0 2775595??.0
.......... 563641.0_ 1553792.0 89947646,0 l
- 10. GROSS ELECTRICAL ENERGY GENERATED (MWM).
540719.0_ 1470934.0 84645175;0
.11. NET WLECTRICAL ENERQY GENERATED (MWM) 100.0 18.0 7R 7
~
- 12. 8' EACTC SE RVICE P ACTOR.......................
100.0 38.9 80.7
- 13. RE ACTOR AV All.Aet LITY P ACTOR....................
100.0 36.7 76.2
~ 14. UNIT SERVICE P ACTOR........................
100.0 36.7
'76.7 l
94.5_
32.8
'64.8
- 18. UNIT CAPACITY P ACTOR (Us ; MOCl.....................
92.1 32.0 63.t
- 17. UNIT CAPACITY P ACTOR tus.ng Doogn MWel............
O.O_
2 7. B.
9 7
- 10. UNIT PORC80 OUTAGE RATE...................
i
- 19. SHUTDOWNS SCHGOUL40 QVER NEXT 8 MONTl's (TYPE, DATE. AND DURATION OF EACHl:
.}
- 20. IF SMUT DOWN AT END OF REPORT PERIOD. ESTIMATED CATE OP STARTUP:
f
- 21. UN'TS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATIONI FORECAST ACHIEVED
?
1 INITIAL CRITICALITY t
. INITIAL ELECTRICITY COMMERCI AL OPtRATION i
6-1.16 9 i
APPENDlX C OPERATING DATA REPORT 00CKET NO.
50-265 Two UldlT DATE COMPLETE 0 llY CVnthin lenek-Short l
309-654-2241 TELEPHONE OMRATING STATW $0000 080191 744
- l. MSPORTil*4 PERl09: 5 2400 08319) CROSS HOUR $ IN REPORTINO PERl00t 2bII M A A. ORPt NO. CAP ACITY (MWe Noth, 769 3, CURR8NTtY AUTHORl280 POW 8R LEVIL (WWilt -
08814N SL8CTRICAL RADNQ IMWel%di 789 N/A
- 3. POWER LEVOL TO W 4M
- 887RICTED (IP ANY) IWWeNeth
- 4. MEASONS POR L /**/ e0N (IP ANYh THIS MosffH YR TO DATE CUesutATIVS 744.0 5316.6 11106s.H N c. 98PI OP HOUR 6.4EACTOR WA8 CRITICAL...............
0.0 0.0 2985.8 L J"4.'DR R488RVE SHUTOOWN HOUR $.......,,,.
744.0 5?$f,,f, 127555,8
- 7. HOUR 8 0tNER ATOR ON LINE..........,.............
Og 0.0 70?.9
- 8. UNIT ffl8RVE SHUTOOWN HOURS.....................
............ 1728721.0 12235885.0 275467706.0
- 9. OR086 4 HERWAL ENtROY CINER Af t0 lWWH)
,,,,,. 83328.0 3960947.0 88422154.0 4
- 10. 06008 Et.lCTRICAL ENERQY QENER ATIO (WWW.....
....,.,.....,,540179.0 3831940.0 83662492,0
- 11. N1T ttECTRICAL LNERGY GENERAff 0 (WWM) 100.0 91.2 77.8
- 12. r E ACTOR SERVICE P ACTOM.................
100.0 91.2 79.6_
- 13. REtiCTOR AV AILASILITY P ACTOM......
100.0 90.3 7 s. 8_
100.0 90.3 76.?
- 19. UNIT AV AIL A tiLITY P ACTOR,,,......................
94.5 85.4 64.6_
- 18. UNIT CAPACITY P ACTOR IUotag WDCI..................... _
92.I 83.3 63.0
- 17. UNIT CA1 ACITY P ACTOR (Usang Dee.gn WWel.................
.0 9.2 7. 9_
- 18. UNlf PORCE D OUT AG E RAf t..........................
- 19. tHUT00WNS SCH6WL80 0VfR NEXT S MONTH 8 (TYPt. DAff. AN0 0VRAT104 07 (ACHh
- 20. IP $ HUT 00WN AT INO OF REPORT PERICO. ($TIMAf f 0 D ATE OP $7ARTUP:
- 31. UNITS IN TEST STATUS (PRIOR TO COMMERCI AL OPERATIONh PORICA$f ACHlfVED INITIAL CRiflCAllTY INITIAL ELECTRICITY COMMERCIAL OPtRAT10N t,16 9
~ -'
APPEN21X B AVERAGE CAILY UNIT POWER 12 VEL DOCXET No. 50-2;4 UNIT one DA g September 5. 1991 COMPLETED BY Cv" thin A. Losek TELEPHONE 309-654-2241 MONTH
^"r"at 1991 DAY AYERACE DAILY MWER LEVEL DAY AYERAGE DAILY POWER LEVEL (MWo b et)
(MWe Net) 716 784 g
gy 651 3
776 gg 786 3
733 723 74I 4
at IOl 755 E
to t
754 78I 4
d 787 756 y
23 780 679 g
34 696 644 g
g 725 726 10 26 II7 656 27 gg 687 7I4 12 3
603 780 13 y
780 775 14 30 780 16 39 74g 694 16 -
INSTRUCTIONS On this form, hst the awrage daily unit power newl in MWeNet for each day m the reporttng month Compute to the newest whole megawatt, These figures will be used to plot a paph for cash reporting month. Note that when maximum dependable capacity is wied f or the nel clestncal rating of the umt, there may os osessions when the daily aversge power levci ettetds the 100'A kne (or the restrwied power Ic+el hnc). In such cases, the average daily urut power output sheet should be footnoted to caplaua the apparent anomaly.
1.164
APPENDIX 3 i
AVL' RACE DAILY UNIT POWER LEVEL i
DOCKET NO. 50-265 UNIT Do DATE 8*Pt**h*' 5.,1991 COMPl,ETED BY Cyntbla A. Losek TELEPHONE 309-654-2241 i
pg g Aunust, 1991 i
DAY AVERAGE DAILY :CWER IKVEL DAY AVERAGE DAILY POWER LEVEL (MWe+ et)
(MWeNet) i-t g7 743 742 757 719 g
gg 720 729 3
gg 730 752 4
N 5
21 761 735 727 696 6
It 739 728 y
23 708 736 g
g4 735 701 g
g 703 739 10 y
767 712 27 gy 743 760 13 g
677 740 gg
.3 694 730 14 30 e
670 682 18 3,
736 3g INSTRUCTIONS On this form, hat the average daily unit power level in MWeNet for each day in the reporting month Compute to the i
neassst whole megawatt.
These figures will be used to plot a graph for cash reporung month. Note that when mammum dependable capac'lty is used tur the net clestncal rating ut the unit, there may be oscasions wheti ths daily average power level escetds the If0A hee (or the rntncted power leiel hnct in such cases, the average daily urut power output sheet should be footnoted to espiaga the apparent anomaly, 1.164 s-v s
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APPENDIX D' UNIT SMUTDOWNS AND ICWEJt REDUCTIONS DOCKET NO.-
50-265
' UNIT NAME
. Unit Two COMPLETED BY Cynthia A. Losek-Short 1
DATE September.5, 1991-REPORT MONTH August 1991 TELEPHONE 309-654-2241 a:
och w"
oDM-hw
$w-fM LICENSEE m@
EVENT o"
DURATION M
gbdg ra.
REPORT NO.
CORRECTIVE ACTIONS /COf9ENTS NO.
DATE
'(HOURS) g i"
91-22 910813 F
5.2 D
5 LCO Entered due to Failure of Secondary Containment Test (T.S. 3.0.A) i 91-23 910826 F
6.0 D
5 LCU Entered due to Unit 2 Diesel Generator being Declared INOP.
i i
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j..
-I-(final) l
i VI.
URIDULBEf'ORIING_REQUIREt!ENIS t
[
The following items are included in this report based on prior commitments to the commission.
A.
tiallLitE ADLRell e.f_Vahe_00e tittions l
There were no Main-Steam Relief Valve Operations for the reporting period.
f B.
ControLROLDIlyLStram Timit!LDaiLfor_UAl1L0ntand_IWo f
There was no Control Rod Drive scram timing data for Units One and Two for f
the reporting period.
f I
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t TS 14
[
l 1
I V11. REEUEllRG_JHEORMlIION The following information about future reloads at Quad-Cities Station was requested in a January 26, 1978, licensing memorandum (78-24) from j
D. E. O'Brien to C. Reed, et al., titled "Dresden, Quad-Cities and Zion Station--NRC Request for Refueling Information", dated January 18, 1978.
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QTP 300-532 i
Revision 2 QUAD CITIES REFUELING October 1989 INFORMATION REQUEST-1.
Unit:
41 Reload:
II Cycle:
12 2.
Scheduled date for next refueling shutdown:
9-5-92 I
3.
Scheduled date for rastart following refueling:
12-5-92
?
t 4.
Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment:
NOT AS YET DETERMINED.
[
I N
5.
Scheduled date(s) for submitting proposed licensing action and supporting information:
NoT AS.YET DETERMINED, 6.
Important licensing considerations associated with refueling. e.g., new
(
or different fuel design or supplier, unreviewed design or performance
)
analysis methods, signiffrant changes in fuel design, new onerating i
procedur(s:
NONE AT PRESENT TIME.
f E
t t
7.
- The number of fuel assemblies.
I a.
Number of assemblies in core:
724 b.
Number of assemblies in spent fuel pool:
1405 t
i 8.
The present licensed spent fuel pool storage capacity and the size of l
any increase in licensed storage capacity that has been requested or'is j
planned in number of fuel assemblies:
f a.-
Licensed storage capacity for spent fuel:
3657 j
b.
Planned increase in licensed storage:
'O p
9.
The projected date of the last refueling that can be discharged to_the t
spent fuel pool assuming the present licensed capacity:
2009 i
t i
APPROVED 1
(final) 14/0395t-OCT 3 01989 I
)
u o.c.o.S.R.
y r
QTP 300-532 Revision 2 QUAD CITIES REFUELING-October 1989 INFORMATION REQUEST 1.
Unit:
42 Reload:
10 Cycle:
11 I
2._
-Scheduled date for next refueling shutdown:
12-28-91 i
3.
Scheduled date for restart following refueling:
3-7-92 4.
W111 refueling or resumption of operatic 1 thereafter reculre a Technical Specification change or other license amendment:
NOT AS YET DETERMINED.
5.
Scheduled date(s) for submitting proposed Itcensing action and supporting information:
NOT AS_YET DETERMINED.
4 1
- 6.
Important licensing considerations associated with refueling, e.g., new or different' fuel design or suppiter, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:
_NONE AT PRESENT TIME.
b T
l 7.
- The number of fuel assemblies, i
a..
Number of-assemblies in core:_
724 i
b.
Number of assemblies in spent. fuel pool:
2287 i
s L
8.
The present licensed spent fuel pool storage capacity and the size of-any increase in licensed storage capacity that has been requestea or is
_ lanned in number of fuel assemblies:
p Licensed storage capacity for spent fuel:
a.
3897
.b.-
Planned increase in Itcensed storage:
0 9.
The projected date of the last refueling that'can be discharged to the spent fuel pool assuming the present licensed capacity:
- 2009 APPROVED (final) 14/0395t OCT 3 01989 1
'r 1
O.C.O.S.R.
?
i VIII. GLOSSARY The following abb.eviations which may have been used in the Monthly Report, are defined below:
ACAD/ CAM - Atmospheric Containment Atmospheric Dilutton/ Containment Atnospheric Honitoring l
ANSI
- American National Standards Institute 1
- Average Power Range Monitor i
ATHS
- Anticloated Transient Hithout Scram l
BHR
- Bolling Hater Reactor CRD
- Control Rod Drive l
- Electro-Hydraulle Control System EOF
- Emergency Operations facility i
GSEP
- Generating Stations Emergenry Plan HEPA
- High-Efficiency Particulate filter HPCI High Pressure Coolant Injection System HRSS-
- High Radiation Sampling System i
IPCLRT
- Integrated Primary Containment Leak Rate Test 1RH
- Intermediate Range Monitor ISI
- Inservice Inspection f
LER
- Licensee Event Report LLRT
- Local Leak R4te Test LPCI
- Low Pressure Coolant Injection Mode of RHRs LPRM
- Local Power Range Monitor.
~
MAPLHGR - Maximum Average Planar Linear Heat Generatio, Rate HCPR
- Minimum Critical Power Ratio MFLCPR
- Maximum fraction Limiting Critical Power Ratio HPC
- Maximum Permissible Concentration i
HSIV
- Main Steam Isolation Valve NIOSH
- National Institute for Occupational Safety and Health PCI
- Primary Containment Isolation
-PC10HR
- Preconditioning Interim Operating Management Recommendations RBCCH
- Reactor Building Closed Cooling Hater. System RBH
- Rod Block Honitor RCIC
- Reactor Core Isolation Cooling System RHRS
- Residual Heat Renoval System i
RPS-
--Reactor P;otection System RHH
- Rod Horth Minimizer SBGTS
- Standby Gas Treatment System SBLC
- Shutdown Cooling Mode of RHRS SDV
- Scram Discharge */olume SRH
--Source Range Monitor TBCCH
- Turbine Building Closed Cooling Hater System TIP
- Traversing Incore Probo TSC
- Technical Support Center TS 14
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