05000368/LER-2002-001, Reactor Coolant System Pressure Boundary Leakage Due to Primary Water Stress Corrosion Cracking of Pressurizer Heater Sleeves
| ML021680047 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 06/12/2002 |
| From: | Cotton S Entergy Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 2CAN060201 LER 02-001-00 | |
| Download: ML021680047 (7) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 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) 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 |
| 3682002001R00 - NRC Website | |
text
-Entergy Entergy Operations, Inc.
1448 SR. 333 Russeliville, AR 72802 Tel 501 858 5000 2CAN060201 June 12, 2002 U. S. Nuclear Regulatory Commission Document Control Desk Mail Station OP1-17 Washington, DC 20555
Subject:
Arkansas Nuclear One - Unit - 2 Docket No. 50-368 License No. NPF-6 Licensee Event Report 50-368/2002-001-00
Dear Sir or Madam:
In accordance with 10CFR50.73(a)(2)(ii)(A), enclosed is the subject report concerning leakage through the Reactor Coolant System pressure boundary.
The enclosure contains no commitments.
Sincerely, eherrie R. Cotton Director, Nuclear Safety Assurance SRC/dh enclosure
-1
2CAN060201 PAGE 2 cc:
Mr. Ellis W. Merschoff Regional Administrator U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 NRC Senior Resident Inspector Arkansas Nuclear One P.O. Box 310 London, AR 72847 Institute of Nuclear Power Operations 700 Galleria Parkway Atlanta, GA 30339-5957 LEREvents~inpo.org
NRC FORM 365 U.S. NUCLEAR REGULATORY APPROVED BY OMB NO. 3150-0104 EXPIRES 6830-2001 (1-2001)
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LICENSEE EVET R T
INuclear Regulatory Commission, Washington, DC 20555-0001, and to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-10202 (3150-0104), Office of Management and Budget, Washington, DC 20503.
FACILITY NAME (1)
DOCKET NUMBER (2)
PAGE (3)
Arkansas Nuclear One - Unit 2 05000368 I
1 OF 5 TITLE(4) Reactor Coolant System Pressure Boundary Leakage Due To Primary Water Stress Corrosion Cracking Of Pressurizer Heater Sleeves EVENT DATE (S)
LER NUMBER (6)
REPORT DATE (7)
OTHER FACILITIES INVOLVED (8)
MO DAY YEAR YER SEQUENTIAL REV MO DAY YEAR FACILITY NAME DOCKET NUMBER NUMBER NO T
1 FACILITY NAME DOCKET NUMBER 04 1 5 2002 2002 001 00 06 1 2 2002 OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR: (Check one or more) (11)
MODE(9 5
l 20.2201(b) l 20.2203(a)(3)(1) 50.73(a)(2)(i)(C) 50.73(a)(2)(vii)
POWER 20.2201(d) l 20.2203(a)(3)(ii)
X 50.73(a)(2)(ii)(A) l 50.73(a)(2)(viii)(A)
LEVEL (10) 000 20.2203(a)(1) 20.2203(a)(4) 50.73(a)(2)(ii)(B) l 50.73(a)(2)(viii)(B)
- - s. 1l 20.2203(a)(2)(i) l l50-36(t)(1)(i)(A) l l50.73(a)(2)(iii) l l50-73(a)(2)(ix)(A)l
- ,gD lZ3()()ii 1l50.36(c)(1)(ii)(A) i l50.73(a)(2)&i)(A) ll5.3a()x 20.2203(a)(2)(iii) 50.36(c)(2) 50.73(a)(2)(v)(A) 73.71 (a)(4) 20.2203(a)(2)(iv) 50.46(a)(3)(ii) 50.73(a)(2)(v)(B) l 73.71 (a)(5) l 20.2203(a)(2)(v) l 50.73(a)(2)(i)(A) l 50.73(a)(2)(v)(C) l OTHER 20.2203(a)(2)(vi) l 50.73(a)(2)(i)(B) l 50.73(a)(2)(v)(D)
Specify in Abstract or (17)
A.
Plant Status At the time this condition was discovered, Arkansas Nuclear One Unit 2 (ANO-2) was in cold shutdown, Mode 5, with a scheduled refueling outage in progress.
The Reactor Coolant System (RCS)
[AB] was in reduced inventory with the Pressurizer [AB] drained.
An additional leaking heater sleeve was identified during heatup from the outage, with the RCS at 545 degrees F and 2200 psi.
B.
Event Description
Six Alloy 600 heater sleeves were found to be leaking in the ANO-2 Pressurizer.
Five of these heater sleeves were identified on April 15, 2002, during plant cooldown.
The remaining leaking heater sleeve was found on April 30, 2002, during plant heatup.
On April 15, 2002, following shutdown for a scheduled refueling outage, visual inspections of the RCS were conducted for evidence of boron in accordance with NRC Generic Letter 88-05, "Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR Plants."
The initial inspection was conducted with the insulation remaining on the Pressurizer lower head.
Five Pressurizer heater sleeve penetrations were determined to be leaking.
Small amounts of boron were discovered at each of the five sleeve penetration interfaces.
The insulation was removed from the heater sleeves and bottom head of the Pressurizer and the heater sleeves were re-inspected.
This inspection confirmed that only the five heater sleeves were leaking.
Inspection of the Pressurizer base metal area surrounding each sleeve indicated that no boric acid wastage had occurred.
On April 30, 2002, during plant heatup, a structural integrity inspection was conducted.
Plant operators observed a residue on another Pressurizer heater sleeve that appeared to be dry boron.
The operators concluded that the residue was caused by an RCS leak, but the leak was not active.
No boric acid wastage was present in the Pressurizer base metal area surrounding the heater sleeve.
As a result of the discovery of this leakage, all Pressurizer and hot leg nozzles were re-inspected to verify RCS nozzle integrity.
The Pressurizer heater sleeves were inspected again following repair and heat-up to normal operating pressure and temperature conditions.
No additional leakage was identified.
NRC FORM 368A (1-2001)
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N U.S. NUCLEAR REGULATORY COMMISSION i
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LICENSEE EVENT REPORT (LER)
FACILITY NAME 1)
DOCKET (2)
LER NUMBER 6 PAGE (3 Yl SEQUENTIAL REVISION NUMBER NUMBER Arkansas Nuclear One - Unit 2 05000368 2002 001 00 3 OF S NARRATIVE (17)
C.
Root Cause The root cause of leakage for all six Pressurizer heater sleeves was determined to be Primary Water Stress Corrosion Cracking (PWSCC).
The heater sleeves in the ANO-2 Pressurizer were fabricated from Alloy 600, which is known to be susceptible to PWSCC.
The Pressurizer heater sleeves were welded with a J-groove weld between the sleeve and the Alloy 600 weld metal cladding inside the bottom head.
All of the sleeves were from one heat of cold-drawn and low-temperature annealed material.
Previous laboratory analysis of this material revealed extensive carbide precipitates that were not coincident with the grain boundaries.
The carbides were intragranular and along prior grain boundaries that existed before the mill anneal heat treatment.
The material exhibited a small grain microstructure and a relatively high yield strength that causes it to be susceptible to PWSCC.
During fabrication the Pressurizer heater sleeves were mechanically reamed to remove local high spots resulting from weld shrinkage and distortion and were not stress relieved after installation.
This imposed additional inner diameter surface stresses and susceptibility to axial PWSCC.
The normal operating temperature for the Pressurizer (approximately 657 degrees F) increases the susceptibility of Alloy 600 heater sleeves to PWSCC, particularly when other material conditions (reaming, poor microstructure, high yield strength) are present.
PWSCC is a failure mechanism that is dependent on time of operation as well as on temperature, stress, and material condition.
A load limit finite stress analysis was performed that indicated that the sleeves closest to the center of the Pressurizer have higher maximum stresses and are, therefore, more susceptible to PWSCC.
This analysis is consistent with the location of most heater sleeves that have failed since a mid-cycle outage in July 2000.
With the exception that it was detected during heatup, leakage from the sixth Pressurizer heater sleeve was similar to that of the other heater sleeves.
It is believed that cooldown thermal stresses at the beginning of the outage placed the J-groove weld region of that Pressurizer heater sleeve in a tensile stress condition, creating a through-wall breach of an existing PWSCC crack.
Subsequent heat-up with the existence of a through-wall crack resulted in leakage and the boric acid residue being found on the heater sleeve.
(17)
Due to the similarities of the six leaking heater sleeves to the twelve leaking heater sleeves found during the mid-cycle outage of July 2000, it was determined that neither nondestructive examination nor laboratory sampling was required to confirm the cause of leakage.
All Pressurizer heaters were inspected during the previous refueling outage and no leaks were identified; therefore, the boric acid leakage had developed since December 2000.
D.
Corrective Actions
The leaking Pressurizer heater sleeves were repaired using a Mechanical Nozzle Seal Assembly (MNSA2) designed to replace the function of partial penetration J-groove welds that attach Alloy 600 nozzles or heater sleeves to the Pressurizer.
The MNSA2 provides a mechanical seal against leakage and positively captures the nozzle, preventing ejection in the unlikely event of complete 360-degree weld failure.
The MNSA2 was designed as an ASME Section III, Class 1, safety-related primary pressure boundary.
The NRC approved use of the MNSA2 for two refueling cycles.
Material testing verified compatibility of the MNSA2 with the pressure boundary materials and environment.
ANO is developing a long range plan for the examination and any necessary repairs of the remaining Pressurizer heater sleeves.
E.
Safety Significance
Based on previous experience, leakage from the six Pressurizer heater sleeves was determined to be due to axial cracking of the heater sleeve.
Axial cracking will not lead to an axial rupture of the sleeve.
Flaws leading to leaks are expected to remain in an axial orientation.
Although there exists a theoretical likelihood for the existence of circumferential flaws, the propensity for these flaws to cause a complete circumferential failure leading to the ejection of a heater sleeve within one operating cycle is remote.
Even though ANO continues to identify the presence of PWSCC cracking on heater sleeves, it is believed that future flaws will remain axial within a given outage cycle and that this does not represent a structurally significant condition.
Therefore, there is no imminent need to perform additional repairs of non-leaking nozzles or to conduct more frequent inspections of the nozzles.
For these reasons, the overall safety significance of this condition was determined to be minimal.
NRC FORM 368A (1-2001)
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U.S. NUGLEAK KE3UATR c;M~yiSSIO I
Page 5 (1-2001)
LICENSEE EVENT REPORT (LER)
FACILITY NAME (1)
DOCKET (2)
LER NUMBER 6 PAGE (3)
YEAR SEQUENTIAL REVISION NUMBER NUMBER Arkansas Nuclear One -
Unit 2 05000368 2002 01E00 5 OFv5 NARRATIVE (17)
F.
Basis for Reportability Using the guidance from Section 3.2.4 of NUREG-1022, "Event Reporting Guidelines -
10CFR50.72 and 50.73," the identified leaks were considered a serious degradation of a principal safety barrier.
Discovery of the first five leaking Pressurizer heater sleeves was reported to the NRC Operations Center at 1104 CDT on April 15, 2002, in accordance with 10CFR50.72(b)(3)(ii)(A).
At 1801 on April 30, 2002, a Notification of Unusual Event was declared due to leakage indication from an additional heater sleeve.
A report was made to the NRC Operations Center at 1813 CDT in accordance with 10CFR50.72(a)(1)(i) and 10CFR50.72(b)(3)(ii)(A).
This report is submitted in accordance with 10CFR50.73(a)(2)(ii)(A).
G.
Additional Information
ANO has reported as Licensee Event Reports (LERs) five conditions involving RCS pressure boundary leakage attributed to PWSCC of Alloy 600 material.
In LER 50-313/90-021-00 (letter 1CAN019112 dated January 21, 1991), ANO-1 reported leakage from an Alloy 600 Pressurizer level sensing nozzle.
In LER 50-313/2000-003-00 (letter 1CAN030001 dated March 16, 2000), ANO-1 reported leaking welds for RCS hot leg level instrumentation nozzles.
In LER 50-313/2001-002-00 (letter ICAN050101 dated May 8, 2001), ANO-1 reported a leaking control rod drive mechanism nozzle.
In LER 50-368/87-003-01 (letter 2CAN088801 dated August 12, 1988), ANO-2 reported leaking Pressurizer heater sheaths.
And, in LER 50-368/2000-001-00 (letter 2CAN080011 dated August 29, 2000),
ANO-2 reported leaking Pressurizer heater sleeves and an RCS resistance temperature detector nozzle.
Corrective actions for these conditions were not intended to prevent recurrence of PWSCC in Alloy 600 material that is subject to this failure mechanism.
Energy Industry Identification System (EIIS) codes are identified in the text as [XX].I