05000529/LER-2012-002, Regarding Condition Prohibited by Technical Specification Due to Low Pressure Safety Injection System Drain Pipe Leak
| ML12356A033 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 12/17/2012 |
| From: | Mims D Arizona Public Service Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 102-06631-DCM/DCE LER 12-002-00 | |
| Download: ML12356A033 (11) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(ix)(A) 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| LER closed by | |
| IR 05000528/2013002 (14 May 2013) | |
| 5292012002R00 - NRC Website | |
text
e 10 CFR 50.73 L A-A subsidiary of Pinnacle West Capital Corporation Dwight C. Mims Mail Station 7605 Palo Verde Nuclear Senior Vice President Tel. 623-393-5403 P.O. Box 52034 Generating Station Nuclear Regulatory and Oversight Fax 623-393-6077 Phoenix, Arizona 85072-2034 102-06631 -DCM/DCE December 17, 2012 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
Dear Sirs:
Subject:
Palo Verde Nuclear Generating Station (PVNGS) Unit 2 Docket No. STN 50-529 License No. NPF-51 Licensee Event Report 2012-002-00 Enclosed please find Licensee Event Report (LER) 50-529/2012-002-00 that has been prepared and submitted pursuant to 10 CFR 50.73. This LER reports a condition prohibited by Technical Specifications resulting from leakage on a Low Pressure Safety Injection pipe drain line outside of the Containment Building while in Mode 5.
In accordance with 10 CFR 50.4, copies of this LER are being forwarded to the Nuclear Regulatory Commission (NRC) Regional Office, NRC Region IV and the Senior Resident Inspector. If you have questions regarding this submittal, please contact Mark McGhee, Operation Support Manager, Regulatory Affairs, at (623) 393-4972.
Arizona Public Service Company makes no commitments in this letter.
Sincerely, DCM/DCE/hsc Enclosure cc:
E. E. Collins Jr.
NRC Region IV Regional Administrator L. K. Gibson NRC NRR Project Manager (electronic / paper)
M. A. Brown NRC Senior Resident Inspector for PVNGS A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway ° Comanche Peak - Diablo Canyon
- Palo Verde
- San Onofre
- South Texas
- Wolf Creek
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 10/31/2013
'*10-2010)
, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
- 13. PAGE Palo Verde Nuclear Generating Station (PVNGS) Unit 2 05000529 1 OF 10
- 4. TITLE Condition Prohibited by Technical Specification Due to Low Pressure Safety Injection System Drain Pipe Leak
- 5. EVENT DATE
- 6. LER NUMBER _
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED MONTH DAY YEAR YEAR SEQUENTIAL REV MONTH DAY YEAR FAITYNMDOKTUBE NUMBER NO.
FACILITY NAME DOCKET NUMBER 10 07 2012 2012 - 002 -
00 12 17 2012
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check all that apply)
El 20.2201(b)
El 20.2203(a)(3)(i)
E3 50.73(a)(2)(i)(C) 0l 50.73(a)(2)(vii) 5 [E
20.2201(d)
El 20.2203(a)(3)(ii)
El 50.73(a)(2)(ii)(A)
El 50.73(a)(2)(viii)(A)
El 20.2203(a)(1)
El 20.2203(a)(4)
El 50.73(a)(2)(ii)(B)
El 50.73(a)(2)(viii)(B)
El 20.2203(a)(2)(i)
El 50.36(c)(1)(i)(A)
El 50.73(a)(2)(iii)
E] 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL [I 20.2203(a)(2)(ii)
El 50.36(c)(1)(ii)(A)
El 50.73(a)(2)(iv)(A)
[E 50.73(a)(2)(x)
El 20.2203(a)(2)(iii)
El 50.36(c)(2)
[I 50.73(a)(2)(v)(A)
El 73.71(a)(4)
El 20.2203(a)(2)(iv)
El 50.46(a)(3)(ii)
El 50.73(a)(2)(v)(B)
El 73.71(a)(5) 0 El 20.2203(a)(2)(v)
El 50.73(a)(2)(i)(A)
El 50.73(a)(2)(v)(C)
El OTHER [E
20.2203(a)(2)(vi) 0 50.73(a)(2)(i)(B)
El 50.73(a)(2)(v)(D)
Specify in Abstract below or in Figure A provides a simplified functional diagram of the Train A SI systems and displays the leak location within the LPSI/SDC system.
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The SI system injects borated water into the reactor coolant system (RCS) (EIIS: AB) to flood and cool the core in the event of a loss of coolant accident (LOCA) to prevent a significant amount of cladding failure along with subsequent release of fission products into the containment. The SI system functions also include core heat removal for extended periods of time following a LOCA and injection of borated water into the RCS to increase shutdown margin following a rapid cooldown of the system due to a secondary steam line break accident (SLBA).
The CS system sprays borated water into the containment atmosphere in the event of a LOCA or a SLBA within the containment to reduce containment pressure and temperature and limit the leakage of airborne activity from the containment. Additionally, CS removes heat from containment following a LOCA by circulation of coolant from the recirculation sumps to the shutdown cooling heat exchangers and back to the containment spray nozzles.
The SDC system uses the LPSI and CS systems to re-circulate RCS coolant through a shutdown cooling heat exchanger in the auxiliary building to remove residual heat from the reactor during normal shutdown activities and to mitigate the consequences of an accident, such as a LOCA or SLBA. Each train of the SDC system consists of two pumps (LPSI and CS), a shutdown cooling heat exchanger and discharge piping with two injection headers which each connect to one of the RCS cold leg loops. Each SDC train includes a SDC suction header and SDC suction isolation valves which connect one of the RCS hot legs to the suction piping of the associated SDC pumps. A SDC train may be operated with one or two SDC pumps to meet operational needs.
The RCS circulates water in a closed cycle, removing heat from the reactor core and internals and transferring it to a secondary (steam generating) system. The steam generators (SGs) (EIIS: AB) provide the interface between the RCS and the main steam system (EIIS: SB). The major components of the RCS are the reactor vessel (EIIS: AB) and two parallel heat transfer loops, each containing one SG and two reactor coolant pumps (EIIS: AB). Each reactor coolant loop contains penetrations which include the pressurizer surge line in one reactor vessel outlet pipe (hot leg); the SI inlet nozzles, one in each reactor vessel inlet pipe (cold leg) and two outlet nozzles to the shutdown cooling system, one in each reactor vessel outlet pipe (hot leg). RCS piping and components are located in the Containment Building (EIIS: NH).
During cold shutdown and refueling operations, the SDC trains are the principal means for decay heat removal. The number of pumps/trains in operation can vary to suit the operational needs. During MODE 5 operations with RCS loops filled, the Limiting Condition for Operation (LCO) for TS 3.4.7 requires one SDC train to be OPERABLE and in operation and either one additional SDC train to be OPERABLE or the secondary side water level of each SG to be greater than 25 percent. The intent of this LCO is to provide forced flow from at least one SDC train for decay heat removal and transport. The flow provided by one SDC train is adequate for decay heat removal. The other intent of this LCO is to require that a second path be available to provide redundancy for decay heat removal. Condition B of TS 3.4.7 applies when either a required SDC train is inoperable or no SDC train is in operation.
Condition B required actions are to immediately suspend all operations involving reduction in RCS boron concentration and to immediately initiate actions to restore one SDC cooling train to an OPERABLE status and in operation.
Valve SIA-V908 is a one inch, ASME Class 2 globe valve connected to a low point elbow on the 12 inch LPSI pipe upstream of 1A cold leg LPSI injection valve in the Auxiliary Building West Piping Penetration Room. The 12 inch, motor operated 1A cold leg LPSI injection valve is a containment isolation valve and is located in the piping penetration room adjacent to containment. A butt weld is used to connect a 3 inch length of one-inch diameter, schedule 40, type 304, stainless steel drain pipe to a nozzle on the 12 inch LPSI pipe elbow.
A socket weld connects the drain pipe to the inlet side of valve SIA-V908 and an elbow with a welded pipe nipple is welded to the outlet of the valve to provide an attachment point for temporary installation of drain hoses and testing apparatus. Valve SIA-V908 is normally closed and the downstream pipe nipple is capped.
- 3.
INITIAL PLANT CONDITIONS
On October 7, 2012, Palo Verde Unit 2 was in Mode 5 (Cold Shutdown), preparing for refueling activities. The RCS cold leg temperature was approximately 98 degrees Fahrenheit and RCS absolute pressure was approximately 110 pounds per square inch.
SDC Train A was OPERABLE and in operation with CS A and LPSI A pumps running in parallel to provide SDC flow. RCS loops were filled with both SG secondary side water levels at approximately 80 percent full. There were no structures, systems, or components inoperable at the time of the event that contributed to the event.
4. EVENT DESCRIPTION
On October 7, 2012, at 22:00, while performing radiation protection surveys, plant personnel noted water on the floor of the 77 foot elevation of the Auxiliary Building West Piping Penetration Room, near the LPSI cold leg 1A injection pipe. At 03:33 on October 8, 2012, two personnel entered the room and subsequently, during personnel contamination monitoring prior to leaving the radiologically controlled area (RCA), found slight amounts of radioactive contamination on their shoes. This contamination was attributed to the water leakage on the floor near the LPSI cold leg 1A injection pipe. The source of the water leakage was initially characterized as packing leakage from drain valve SIA-V908 at 05:28 on October 8, 2012.
Subsequently, with the piping insulation removed, an examination of the drain pipe upstream of valve SIA-V908 identified a through-wall defect on the weld that attaches the drain pipe to the nozzle on the LPSI cold leg 1A injection pipe. The leak rate was estimated to be approximately 0.25 gallons per minute. Figure B provides a sketch of the drain pipe configuration.
When informed of the through-wall leak on the inlet pipe for valve SIA-V908, Operations personnel declared SDC Train A inoperable and entered TS 3.4.7 Condition B at 13:30 on October 8, 2012. Operations personnel verified no operations that involved reduction of RCS boron concentration were in progress and actions were initiated to place SDC Train B into operation as the OPERABLE SDC train. SDC Train B was placed in service and SDC Train A was secured and isolated. Condition B of TS 3.4.7 was exited at 16:39 on October 8, 2012, with SDC Train B OPERABLE and in operation and both SG secondary side water levels greater than 25 percent. No evolutions that would have reduced RCS boron concentration were conducted during the period from the first identification of water on the floor near valve SIA-V908 on October 7 through exit of TS 3.4.7 Condition B at 16:39 on October 8, 2012.
Figure B LPSI Header 1A Injection Pipe and Drain Pipe / SIA-V908 Configuration on October 8, 2012 1 12 inch LPSI Injection Pipe to RCS CL 1A Leak at butt weld between nozzle and drain pipe in place Elbow, welded in Nipple, welded in place, with threaded end pipe cap Pipe hanger
5. ASSESSMENT OF SAFETY CONSEQUENCES
This event did not adversely affect the health and safety of the public and there were no actual safety consequences as a result of this event. The event did not result in any challenges to the fission product barriers. The personnel contaminations did not require assignment of additional radiation dose to the individuals and did not result in the spread of loose surface contamination outside the RCA. The leakage did not result in the release of airborne radioactive material above monitored baseline effluent activity.
A preliminary structural evaluation of the affected weld concluded that the piping retained sufficient load carrying capability to withstand design basis loading conditions including Safe Shutdown Earthquake (SSE) loads. This indicates the weld would have maintained structural integrity given an SSE at the time the defect was identified. Additional engineering evaluations of the structural integrity of the weld and potential safety consequences of this event are in progress. An LER supplement will be provided to report the results of those evaluations.
6. CAUSE OF THE EVENT
The weld defect resulted from the installation of a temporary drain fitting which was left attached to the pipe nipple downstream of valve SIA-V908 when Train A SDC was returned to service following maintenance in December 1991. Piping thermal growth occurred when SDC was placed in operation which caused the SIA-V908 assembly to contact an adjacent pipe hanger (see Figure B) and act as a restraint to system vibrations that occur during operation. As a result, a defect was initiated in the weld due to abnormally high cyclic stresses induced when the SIA-V908 assembly was restrained by contact with the pipe hanger during SDC operations.
Prior to November 1991, insufficient clearance between valve SIA-V908 and the pipe hanger prevented installation of drain fittings. In November 1991, following installation of a new SIA-V908 valve, the clearance was increased which then allowed the installation of a temporary drain fitting during maintenance activities. The temporary drain fitting was left installed when the system was restored to service in December 1991 and remained until May 1993. During that time, SDC operations resulted in high cyclic stresses being imparted on the weld. In May 1993, the design of the outlet side of valve SIA-V908 was modified to install the current elbow and nipple configuration and correct the interference problem such that no further contact with the adjacent pipe hanger occurred. This design change modified only the outlet side of the valve such that the weld upstream of SIA-V908 (which contained the defect) was not worked on. During the time from May 1993 to October 2012, the defect propagated slowly from high cycle fatigue during normal system operations until the pipe wall was breached during Train A SDC operations in refueling outage 2R17.
The cause of this event was determined to be inadequate guidance to ensure temporary fittings on safety-related fluid systems were removed prior to placing the system in service.
7. CORRECTIVE ACTIONS
To correct the weld defect, the subject drain pipe and valve SIA-V908 assembly was replaced and the weld repaired on October 11, 2012.
To evaluate the extent of condition, bare pipe weld visual examinations of the similar LPSI injection drain pipe locations were completed by qualified in-service inspection personnel in all three PVNGS units by October 10, 2012. The examinations did not identify any visually observable defects on the inspected components. Also, there were no indications of mechanical binding in any of these additional locations.
To prevent recurrence, procedures will be revised to require that systems with capped pipe ends be returned to their design configuration with fittings removed and pipe caps tightened when maintenance activities are completed.
To address the extent of cause, additional piping system evaluations and walkdowns of safety-related systems are planned to identify similar conditions in which vent or drain fittings and piping configuration may result in binding and subsequent potential impact on the pipe integrity. Visual examinations of drain pipe welds will be performed based on the results of the evaluations and walkdowns.
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8. PREVIOUS SIMILAR EVENTS
PVNGS reported a similar event under LER 50-528/2004-001 -00 in which pressure boundary leakage was discovered on a Unit 1 HPSI recirculation drain pipe socket weld upstream of drain valve SIA-V056. The cause was vibration-induced, high cycle fatigue weld failure due to a pipe support that should have been removed during a prior pipe support modification. The modification was intended to resolve vibration-induced socket weld failures on RCS and SDC system branch pipes inside the Containment Building. The corrective actions to identify the extent of condition of the 2004 event were to inspect other SDC Train A suction line supports across the station to verify conformance with pipe support design to ensure a similar vibration-induced socket weld failure mechanism did not potentially exist.
The root cause of the 2004 event was not related to a failure to remove a temporary drain fitting and the extent of condition inspections would not have identified examples in which there were potential interference problems with temporary drain fittings left installed.
Therefore, the corrective actions for the 2004 event would not have prevented the event reported in this LER.
NRC FORM 396A (10-201071 PRINTED ON RECYCLED PAPER