05000362/LER-2006-003, For Reactor Coolant System Pressure Boundary Leak Caused by Incomplete Compression of a Mechanical Nozzle Seal Assembly Grafoil Seal
| ML061500428 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 05/26/2006 |
| From: | Breig D Southern California Edison Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LER 06-003-00 | |
| Download: ML061500428 (5) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 3622006003R00 - NRC Website | |
text
SOUTHERN CALIFORNIA EDISON An EDISO' IVT.*R\\,rIOU.%A I Company Daniel P. Breig. P.E.
Station Manager San Onofre May 26, 2006 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555-0001
Subject:
Docket No. 50-362 Licensee Event Report No. 2006-003 San Onofre Nuclear Generating Station, Unit 3
Dear Sir or Madam:
This submittal provides Licensee Event Report (LER) 2006-003 for a reactor coolant system pressure boundary leak caused by incomplete compression of a Mechanical Nozzle Seal Assembly Grafoil Seal. This event did not affect the health and safety of either plant personnel or the public.
If you require any additional information, please contact me.
Sincerely, Unit 3 LER No. 2006-003 cc:
B. S. Mallett, NRC Regional Administrator, Region IV C. C. Osterholtz, NRC Senior Resident Inspector, San Onofre Units 2 & 3 P.O. Box 128 San Clemente. CA 92674-0128 949-368-9263/PAX 89263 Fax 949-368-6183 breigdp@songs.sce.com
Abstract
On March 29, 2006, SCE initiated a controlled shutdown of Unit 3 in order to perform an inspection for a problem identified on Unit 2 (see LER 3-2006-002). At approximately 1450 PDT on March 29, 2006, with Unit 3 in Mode 4, SCE identified boric acid crystals on the Mechanical Nozzle Seal Assembly (MNSA) installed on the Unit 3 pressurizer Resistance Temperature Detector (RTD) mechanical nozzle. SCE inspected and confirmed RCS leakage past the MNSA seal and is reporting this occurrence in accordance with 10CFR50.73(a)(2)(i)(B) as a condition prohibited by Technical Specifications.
SCE concluded that the RCS leak was caused by (1) primary water stress corrosion cracking of the pressurizer nozzle and (2) incomplete compression of the MNSA grafoil seal when the MNSA was installed (March 1998).
SCE removed the leaking MNSA and repaired the nozzle with Inconel 690 material. In addition, the two remaining MNSAs at Unit 3 were removed and the nozzles replaced with Inconel 690 material.
There are no MNSAs currently in use at San Onofre Unit 2 or Unit 3.
The safety significance of this event is minimal.U.S. NUCLEAR REGULATORY COMMISSION (7-2001)
LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION
- 1. FACILTY NAME
- 2. DOCKET NUMBER
- 6. LER NUMBER PAGE ()
EASEQUENTIAL REV NO San Onofre Nuclear Generating Station (SONGS) Unit 3 0500362 NUMBER 30 2of 40 050003 200
- - 003-100 Plant:
San Onofre Nuclear Generating Station (SONGS) Unit 3 Discovery Date:
March 29, 2006 Reactor Vendor:
Combustion Engineering Mode:
Mode 4 - Hot Shutdown Power:
0 percent
Background
Primary water stress corrosion cracking (PWSCC) of Alloy 600 causes nozzles [NZL] installed in Reactor Coolant System (RCS) [AB] piping and the pressurizer [PZR] to develop cracks. At SONGS, in some cases, cracking also resulted in very minor RCS leakage (reported to the NRC in LERs 3-1986-003, 2-1992-004, 3-1995-001, 3-1996-004, 3-1997-001, and 2-1997-004).
Southern California Edison (SCE) used Mechanical Nozzle Seal Assemblies (MNSAs) to address PWSCC at six locations in Unit 2 and three locations in Unit 3. Some of these were installed as a preventive measure even though the nozzles had no indication of leakage.
MNSAs were designed to provide an external seal for instrument nozzles and to prevent a nozzle from ejecting in the event of nozzle failure. A MNSA compresses a grafoil seal against the exterior of the vessel parent material and is held in place by four or six bolts threaded into shallow holes drilled into the vessel parent material around the subject nozzle (see attached diagram of a MNSA).
This essentially moves the pressure boundary from the original nozzle weld to the grafoil seal.
As of March 2006, SCE had removed all Unit 2 MNSAs and replaced the nozzles with Inconel 690 material ("half-nozzle" repair technique). SONGS was planning to remove the remaining Unit 3 MNSAs and replace the nozzles during the upcoming Unit 3 Cycle 14 refueling outage (40 2006).
In Modes 1, 2, 3, and 4, Technical Specification (TS) 3.4.13 prohibits any pressure boundary leakage from the Reactor Coolant System (RCS). If pressure boundary leakage exists, SCE is required to place the Unit in Mode 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in Mode 5 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. The TS basis includes leakage past a MNSA as RCS pressure boundary leakage.
Description of Event
On March 29, 2006, SCE initiated a controlled shutdown of Unit 3 (see LER 3-2006-002). At approximately 1450 PDT on March 29, 2006, with Unit 3 in Mode 4, as part of the normal visual inspection for RCS leakage inside containment, SCE identified boric acid crystals on the MNSA seal installed on the Unit 3 pressurizer Resistance Temperature Detector (RTD) mechanical nozzle (3TE-0101). (This MNSA had been installed in March 1998 as a preventive measure as the nozzle had no indication of leakage at that time). Subsequently SCE inspected and removed the MNSA and confirmed RCS leakage past the MNSA seal. SCE repaired the nozzle by replacing it with Inconel 690 material ("half nozzle" repair technique).
SCE found no evidence of boric acid when this MNSA was last inspected on May 5, 2005. Based on radionuclide analysis, SCE determined that the nozzle began leaking approximately one year ago, and concluded that the MNSA began leaking some time after May 5, 2005 (and during Cycle 13 operation). Consequently, SCE is reporting this occurrence in accordance with 1 OCFR50.73(a)(2)(i)(B) as a condition prohibited by Technical Specifications.U.S. NUCLEAR REGULATORY COMMISSION (7-2001)
LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION
- 6. LER NUMBER PAGE (3)
IEA SEQUENTLAL REV NO San Onofre Nuclear Generating Station (SONGS) Unit 3 05000362 YR NUMBER 0
3 of 4 12006
- - 003-0
Cause of Event
The boric acid crystals on the exterior of the MNSA indicate that both the nozzle and the MNSA leaked.
SCE believes the pressurizer nozzle leak was caused by PWSCC. SCE performed eddy current examination of the pressurizer RTD nozzle and detected three axially oriented indications on the inside diameter approximately 13.5 inches inside the tube. The approximate length of the indications ranged from 0.25 to 0.50 inch. These results are indicative of PWSCC.
SCE concluded the MNSA seal leak was caused by incomplete compression of the grafoil seal when it was installed (March 1998). The incomplete compression was most likely due to the bolts not reaching a depth that would have compressed the seal to the designed values. This could have resulted from (1) the threaded holes not being machined deep enough, and/or (2) insufficient thread lubrication causing the bolts to indicate the required torque values prior to fully compressing the seal. SCE confirmed the MNSA was installed in accordance with the vendor's procedure; however, the procedure did not require verification of seal compression by direct measurement when this MNSA was installed.
In November 2000, SCE became aware that another nuclear plant experienced a MNSA that was installed in a "cocked" position. In response that event, the vendor improved their MNSA installation procedure to include a requirement to measure the gap between the lower flange and the vessel surface to verify seal compression (in addition to other procedure changes). SCE was aware of the procedure change and the new requirement to verify seal compression for MNSAs installed after the procedure revision date. SCE reviewed all SONGS MNSAs and concluded that only MNSA 3TE-01 01 was vulnerable to cocking. In January 2001, SCE inspected 3TE-01 01 and determined it was not cocked, but did not also verify MNSA seal compression. SCE now views this as a missed opportunity to correct this condition.
Corrective Actions
SCE performed the following corrective actions:
- 1. SCE removed the MNSA seal on the Unit 3 pressurizer RTD nozzle after performing inspections in an effort to determine the cause of the failed seal.
("half nozzle" repair technique).
- 3. SCE removed the two remaining MNSA seals at SONGS Unit 3. Inspection of the seals indicated they had been installed with adequate compression of the grafoil seal. In addition, no indication of leakage was observed at the associated nozzles and eddy current examinations revealed no detectable indications of flaws. Nevertheless, SCE replaced the nozzles with Inconel 690 material ("half nozzle" repair technique).
Safety Significance
The safety significance of this event is minimal. MNSAs are designed and maintain the ability to prevent ejection of a nozzle even if a complete circumferential crack were to occur. They also are intended to provide a seal at the surface of the parent material to prevent leakage should a crack inU.S. NUCLEAR REGULATORY COMMISSION (7-2001)
LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION I6.
LER NUMBER PAGE 43)
YEAR SEQUENTIAL REV N San Onofre Nuclear Generating Station (SONGS) Unit 3 05000362 1
- - 00E -
NUMBE 1
1 2006
--003-00 1 of the nozzle propagate throughwall. In this case, the MNSA remained capable of performing its safety function of preventing nozzle ejection even though it did not provide a leak tight seal. SCE's RCS visual inspection program also provided identification of this nozzle leak.
Finally, the consequences of a postulated nozzle ejection would be bounded by the existing small break Loss of Coolant Accident evaluation in Chapter 15 of the Updated Final Safety Analysis Report for San Onofre Units 2 and 3.
Additional Information
Previous occurrences: SCE has not previously reported a failure of a MNSA to prevent leakage. As discussed above, SCE previously reported instances of RCS pressure boundary leaks at SONGS due to PWSCC (LERs 3-1986-003, 2-1992-004, 3-1995-001, 3-1996-004, 3-1997-001, and 2-1997-004).
Side Pressurizer RTD Mechanical Nozzle Seal Assembly (for illustrative purposes only)
Grafoil Seal