ML20207L658
| ML20207L658 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 09/29/1988 |
| From: | Hunsader S COMMONWEALTH EDISON CO. |
| To: | Murley T Office of Nuclear Reactor Regulation |
| References | |
| TASK-3.D.1.1, TASK-TM 5163K, NUDOCS 8810170389 | |
| Download: ML20207L658 (5) | |
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[ _ ' Commonwealth Edloon One First National Piars, Chicago, lilinois
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Address Reply la Post Office Box 767 v
Chicago, litinois 60690 0767 September 29, 1988 Mr. Thomas E. Murley, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washingtou, DC 20555 Subjects Braidwood Station Unit 1
'INI Item III. D.1.1 "Primary Coolant Sources Outside Containment" NRC Docket No. 50-456 References (a) NUREG-1022, Supplement 1, dated September, 1986 i
(b) September 25, 1987 C. Norelius letter to C. Reed (NRC Open Item 456/87-029-02)
Dear Mr. Murley In reference (a), the NRC staff provided their review of Braidwood Station's leak reduction program. The program was found by the NRC staff to meet the requirements of 'INI Action Plan Item III.D.1.1.
However, the initial leak-test results were ;equired to be submitted for review to complete the actions for this TMI Item.
The purpose of this letter is to provide those results.
Attached is a copy of the "Primary Coolant Sources Outside Containment, Initial Examination Sununary Report" for Braidwood Unit 1.
This report satisfies the commitments presented in the Byron /Braidwood FSAR, j
Appendix E.77.
Please direct any questions concerning this matter to this office.
ll Very truly yours, A c. 9 w S. C. Hunsader Nuclear I,1 censing Administrator gd/
att.
cca W Forney (RIII)
S. Sands (HRR)
Braidwood Resident Inspector I
5163K lh4h I
8810170309 880929 l l PDR ADOCK 05000456 P
PNU t
COMMONWEALTH EDISON BRAIDWOOD NUCLEAR POWER STATION Unit 1 l
PRIMARY COOLANT SOURCES OUTSIDE CONTAINMENT l
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l Initial Examination Summary Report July 26,1988 l
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(7512z)
PRIMARY COOL 3NT SOURCES OUTSIDE CONTAINMENT mitial Examination Summary Repor_t In accordance with Technical Specification 6.8.4., integrated leak tests were performed on piping systems as described in Byron /Braidwood Final Safety Analysis Report (FSAR), Appendix E.77, "Primary Coolant Sources Outside Containment." The FSAR position was developed to meet the requirements of NU REG-0737 (Ill.D.I.1).
The Potentially Radioactive Leak TestinF (PRLT) Program is described in Station Procedures BwVP 200-12 and BwVP 200-12A1. These procedures reference station surveillance BwVS 4.~10.-4, BwVS 4.10-5, BwVS 290-1, and BwVS 290-2 which were utill cd to execute the visual examinations for leakage.
The ASME Class 2 and 3 systems were examined in accordance with the ASME Boiler and Pressure Vessel Code,Section XI,1983 Edition including Addenda through Summer 1983. Non-ASME Class (Class D) systems were examined using guidance from Section XI and ANSI B.31.1.
Leakage observed during the course of the examinations was conservatively quantified and documented. Work requests were then initiated to repair the leaking components as deemed necessary.
Braidwood file location 1S1-10 contains the completed station procedure BwVP 200-12A1, "Leakage Testing Requirements for Potentially Radioactive Components Outside Containment, Checkoff List". The Checkoff List contains all the components examined, which surveillance was used to execute the visual examination on the component, and the date the surveillance was performed.
The following systems, or portions thereof (see FSAR for exemptions), were visually examined for evidence of leakage: Chemical and Volume Control (CV),
Containment Spray (CS), Radioactive Waste Gas (GW), Offgas (OG), Residual Heat Removal (RH), Safety injection (SI), Fuel Pool Cooling (FC) and Process Sampling (PS). The total estimated leakage is approximately 0.0416allons per hour of fluid and approximately 15.59 SCFH (0.26 SCFM) gaseous. It should be noted, this is a conservative estimate due to continuing maintenance efforts to contain the identified,takage. Attachment A contains a system breakdown of identified leakage.
The only exception to the nquired examination boundaries is the Fuel Pool which is a part of the Fuel n'ool Cooling System (FC). There is no fuel being stored in the pool at this time and therefore it was not practical to test. The Fuel Pool will be included in fature inspections after it is put into use.
The general jeakage criteria to te applied during the first fuel cycle will be to continue to initiate work requests to repair identified leakage. Work requests of this type will receive an ALAR A review to determine the urgency of repair based on ALARA concerns.
(7512z)
Page 1 of 2 ATTACHMENT A Chemical and Volume Control System (CV):
M DESERIPTION AMOUNT IFIT-142 Packing Leak 0.0008 gph 1CV01PA Pump Seal Leak 0.0008 gph Containment Sorav System (CS):
M DISfRIPTION AMOUNT ICS007B Packing Gland 0.03 gph ICS 38AB-1/2" Threaded Conn.
0.0008 gph Fuel Pool Cooline (FC):
M DESCRIPTION AMOUNT No observed leakage Rad Waste Gas (GW):
M DESCRIPTION AMOUNT ICV 8157 Packing Leak Not Measured 0GW054 Packing Leak Not Measured OWX254 Seat Leakage Note - 1 OGW5019A Seat Leakage Note - 1 OGW5019B Seat Leakage Note - 1 OGW038 Seat Leakage Note - 1 0AB028 Seat Leakage Note - 1 0AB029 Seat Leakage Note - 1 2GW004 Seat Leakage Note - 1 1RE9160A Seat Leakage Note - 1 1RE9157 Seat Leakage Note - 1 2RE9160A Seat Leakage Note - 1 2RE9157 Seat Leakage Note - 1 0AB8627A Seat Leakage Note - 1 0AB8627B Seat Leakage Note - 1 OAB8601 Seat Leakage Note - 1 NOTE-1:
The above list represents valves used to isolate the suction side of the Waste Gas Compressors (Vent Header). A;; the valves were in the CLOSED position for the purpose ur this test. Totalleak rate was measured at 3.19 SCFH (0.05 SCFM) which is within acceptance criteria of the surve;11ance. All of the valves were solution film tested (snooped) for external leakage with none being found. The leak rate obtainev during the test was attributed to leakage past the valve seats and therefore contained within the system. No further action taken.
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Page 2 of 2 Offras System (OG):
EEN DESCRIPTION AMOUNT 00G061 Seat Leakage Note - 1 00G062 Seat Leakage Note - 1 10G082 Seat Leakage Note - 1 LOG 083 Seat Leakage Note - 1 LOG 084 Seat Leakage Note - 1 10G085 Seat Leakage Note - 1 00G063 Seat Leakage Note - 1 00G064 Seat Leakage Note - 1 NOTE-1:
The above list represents the test boundary valves used to isolate the Unit 1 Offgas System with the "A" Hydrogen Recombiner. All of the valves were in the CLOSED position for the purpose of this test. Total leak rate was measured at 12.4 SCFH (0.21 SCFM) which is within the acceptance criteria of the surveillance. All of the valv-within the test boundary were solution film tested (snoopea; for external leakage with none being found. The leak rate obtained during the test was attributed to leakage past the valve seats and therefore contained within the system. No further action taken.
Process Sampje System (PS):
EEN DESCRIPTION AMOUNT IPS9355B Packing Gland 0.002 gph IPS9354B Packing Gland 0.0008 gph Residual Heat Removal System (RH):
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EfB DESCRIPTION AMOUNT l
1RH8725A Pipe Cap 0.0008 gph 1RH01PB Pump Seal 0.0008 gph (2) Pump Casing Bolts 0.0008 gph Safety Inlection (SI):
EEN DESCRIPTION AMOUNT IS!027D Packing Gland 0.003 gph (75122)
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