ML20214K861
| ML20214K861 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 05/22/1987 |
| From: | Spangenberg F ILLINOIS POWER CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-3.D.1.1, TASK-TM U-600947, NUDOCS 8705290075 | |
| Download: ML20214K861 (6) | |
Text
t U-600947 L30-87 (05-22) 1A.120 ILLINDIS POWER 00MPANY IP CUNTON POMR STATION. P 0. BOX 678. CUNTON ILUN0;S 61727 May 22, 1987 NUREG 0737 III.D.1.1 Docket No. 50-461 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C.
20555
Subject:
Clinton Power Station (CPS)
NUREG 0737, TMI Action Plan Item III.D.1.1 Lenkage Reduction Program
Dear Sir:
TMI Action Plan (NUREG 0737) Itera III.D.1.1 established a requirement to reduce and control leakage in nyntemn outside of the containment in nuclent power plants. This action plan requirement contains criteria to be used for implementing a program to reduce leakage from nyntems outnide containment that would or could contain highly radioactive fluids during a serious trannient or accident to as low as practical levels.
CPS FSAR Appendix D Item III.D.l.1 describen the leakage reduction program for Clinton Pownr Station. This program utilizen walkdowns to identify leakage from portions of systems outside containment that would or could contain highly radioactive fluids af ter n Losn of Coolant Accident (LOCA).
In canes where lenkage in determined to be excessive, a Maintennnce Work Requent is initiated to correct the leakage problem.
CPS Supplementary Safety Evaluation Report (SSER) No. 5 indicated a requirement for Illinois Power Company to provide the NRC Staff with the initial leak rate tent resu?ts 120 dayn after fuel lond. Due to the extended period between receipt of the operating licenne and plant hentup, it was necessary to request an extennion of ti'ne beyond the 120 dayn since reactor prennure in required for system prennurization during some portions of the leakage monitoring effort.
In SSER No. 8 the NRC staff necepted thin requent for extension and required that the leakage resultn be provided 30 days after reaching 5% of rated power or 30 dayn after obtaining a full-power licenne, whichever cornen Inter. All practient data collection has been completed in accordance with CPS Procedure 1019.07, "Lenkage Reduction and Monitoring Program." A sun. mary of the initial lenk rate tent renultn in provided in the attachment to this letter. Areas where data collection van not practient are nino identified in the attachment with appropriate juntification.
070D2}007D070522DOCKOD00g1 DH
r t'- 600947 L30- 87(05-22) 1A.120 If you should have any questions concerning the leakage reduction program results, please contact me.
Sincerely yours, f
)
F. A. Spabg h
Manager - Licensh.ng and Safety AJil/bsa Attachment cc:
B. L. Siegel, NRC Clinton Licensing Project Managtr NRC Resident Office Illinois Department of Nuclear Safety Regional Administrator, Region III, USNRC i
1
U 600947 L30 87(05-22) 1A.120
{
Initial Results of the TMI Action Plan Item III.D.I.1 Leakage Reduction Program Plant Systes Procedure Used Location of Leakage System Durine Leakare Monitoring Leakage Observed Rate Comment Reactor Core STP-14-1 Startup Test Orifice IE51-D006 on the Approximately MWR C30578 prepared to Isolation Procedure for RCIC test flow line to the I drop / min.
correct this leakage.
Cooling (RCIC)
RCIC Storage Tank.
Valve IE51-F046 on Lube Approximately MWR C30577 prepared to 011 Cooler water supply 10 drops / min.
correct this leakage.
line.
Residual Heat 9053.07 "RHR Pu=ps A.
Valve IE12-F017A, RRR Approximately MRR C34826 prepared to Removal (RER)
B, C Operability Test" Pump A suction relief 63 drops / min.
correct this leakage.
l Loop A valve.
j Valve IE12-F003A on the Approximately MWR C40825 prepared to i
return line from RHR 19 drops / min.
correct this leakage.
I Heat Exchanger A.
Valve IE12-F048A on the Approximately MWR C35479 prepared to i
l RHR Heat Exchanger A 1 gallon / min.
correct this leakage.
l bypass line.
1 Valve IE12-F087A on the Approximately MWR C24883 prepared to l
RCIC steam supply bypass 7 drops / min.
correct this leakage, line to the RRR Heat Exchanger.
Valve IE12-F052A on the Small puddle MWR C31311 prepared to RCIC steam supply line of water correct this leakage.
to the RER Heat observed on Exchanger.
the valve
- packing, i
j 1
i l
.. m
_ _.._ _. _ _. _ _ __ __....__.. _ _ _ _ _._...__...-.=__._ _. _.
l U G00947 L30JB7(05-22)
IA.120 Plant System Procedure Used Location of Leakage System During Leakage Monitoring Leakage Observed Rate Comment Valve IE12-F053A on the Small puddle MWR C49293 prepared to Line Connecting RHR to of water correct this leakage.
Feedwater for Shutdown observed on i
Cooling Mode.
the valve packing.
Residual Heat 9053.07 "RHR Pumps A,B, Valve IE12-F017B, RHR Approximately No action required.
Removal (RRR)
C Operability Test Pump B suction relief 2 drops / min.
Loop B valve.
Valve IE12-F031B, RHR Approximately No action required.
Pump B discharge check 2 drops / min.
valve.
Orifice IE12-D003B on Approximately No action required, flow return line to the 3 drops / min.
Suppression Pool.
Valve IE12-F087B on the Slight No action required.
Steam Supply from RCIC, wetness around for Steam Condensing packing.
Mode.
. Valve IE12-F047B on the Approximately No action required.
RHR Heat Exchanger 2 drops / min.
supply line.
Valve IE12-F052B on the Approximately No action required.
RCIC steam supply line 4 drops / min.
to the RHR Heat Exchanger.
Residual Heat Valve IE12-F395 on Water Valve No action required.
Removal (RHR)
Leg Pump piping.
components and Loop C floor wet,' no
.quantifiable leakage.
I 2
U 600947 L30 87(05-22) lA.120 Plant System Procedure Used Location of Leakage System During Leakage Monitoring Leakage Observed Rate Comment l
Valve 1E12-F105 on the Approximately No action required.
suction line from the 4 drops / min.
Suppression Pool.
High Pressure 9051.01 "HPCS System Valve IE22-F010 on the Approximately MWR C49601 prepared to Core Spray Pump Operability" HPCS return line to the 20 drops / min.
correct this leakage.
(HPCS)
RCIC Storage Tank.
Valve 1E22-F011 on the Standing Water No action required.
HPCS return line to the observed on RCIC Storage Tank.
top of retain-ing ring.
Valve IE22-F023 on the Moisture from No action required.
HPCS test return line to packing seep-
)
the Suppression Pool.
ing up past re-l taining collar.
l l
Orifice 1E22-D002 on the Minor seepage No action required.
i HPCS return line to the on lower flange RCIC Storage Tank.
of the Orifice.
Valve IE22-F004 on the Seepage from No action required.
HPCS injection line, stem packing i
and valve flange.
Low Pressure 9052.01 "LPCS Opera-Valve IE21-F012 on the Approximately No action required.
Core Spray bility Checks" LPCS test returr. line to I drop / min.
I (LPCS) the Suppression Pool.
Flow Element IE21-N552 Approximately No action required.
l on the Water Leg Pump 1 drop / min.
piping.
Combustible N/A N/A N/A Gas Control H /0 Analfzers l
3
i U 600940 L30- 87(05-22) 1A.120 Plant System Procedure Used Location of Leakage System During Leakage Monitoring Leakage Observed Rate Comment Containment N/A (This portion of None Noted N/A Monitoring system observed under
~
(Suppression static head conditions.
G Pool Level The gaseous portion of Measurement the system was not Portion of covered by this leakage System) monitoring program.)
Suppression N/A (This portion of None Noted N/A Pool Makeup system observed under (Water Level static head conditions.
Measurement The gaseous portion of Portion of the system was not System) covered by this leakage, monitoring program.)
Post Accident 3222.12 " PASS Panel None Noted N/A
~
Samp' ling.
Operation" (PASS panel Syst,em.(PASS) was pressurized only with a reactor coolant j
sample.)
1 The portion of these systems that is located inside the Auxiliary Building Steam tunnel was not inspected during the leakage reduction program because of the limited accessibility of this area and because of ALARA considerations.
Significant leakage occurring in the tunnel would be identffied by the leak detection system.
2 The H /0 Analyzers were not monitored for leakage during this program because the pressure in the 2 2 lines is near atmospheric pressure. Gaseous leakage from piping between the containment and analyzer skids is acceptable per hydrostatic test HTP-CM-02.
Gaseous leakage from the skids is acceptable per special test XTP-CM-01.
3 Gaseous portions of these systems were not monitored for leakage during this program because the pressure in the lines is near atmospheric pressure. These instrument lines are part of the pressure boundary for the integrated leak rate test which was successfully completed.
4