05000327/LER-2012-001, Regarding Unanalyzed Condition Affecting Essential Raw Cooling Water System Due to External Flooding
| ML13044A012 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 02/08/2013 |
| From: | John Carlin Tennessee Valley Authority |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LER 12-001-00 | |
| Download: ML13044A012 (11) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 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)(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 |
| 3272012001R00 - NRC Website | |
text
Tennessee Valley Authority, Post Office Box 2000, Soddy Daisy, Tennessee 37384-2000 February 8, 2013 10 CFR 50.73 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Sequoyah Nuclear Plant, Units 1 and 2 Facility Operating License Nos. DPR-77 and DPR-79 NRC Docket Nos. 50-327 and 50-328
Subject:
Licensee Event Report 50-327 / 2012-001, "Unanalyzed Condition Affecting Essential Raw Cooling Water System due to External Flooding" The Tennessee Valley Authority is submitting this report in accordance with 10 CFR Part 50.73(a)(2)(ii)(B), for a condition that placed both units in an unanalyzed condition that significantly degraded plant safety; (a)(2)(v)(A), for a condition that could have prevented the fulfillment of the safety related function of Essential Raw Cooling Water (ERCW) system needed to shutdown the reactor and maintain it in a safe shutdown condition; and (a)(2)(v)(B), for a condition needed to remove residual heat from various components cooled by the ERCW system.
There are no regulatory commitments contained in this letter. Should you have any questions concerning this submittal, please contact Mr. James Proffitt, Sequoyah Site Licensing Manager at (423) 843-6651.
Respectfully, John T. Carlin Site Vice President Sequoyah Nuclear Plant Enclosure: Licensee Event Report -
cc: Regional Administrator-Region II NRC Senior Resident Inspector - Sequoyah Nuclear Plant
U.S. Nuclear Regulatory Commission Page 2 February 8, 2013 JTJ: SKD Enclosure bcc (Enclosure):
NRC Project Manager - Sequoyah Nuclear Plant Institute of Nuclear Power Operations D. M. Babylon S. M. Connors C. Coovert C. P. Dieckmann Jr.
S. K. Dunn M. Hunter D. E. Jernigan H. Lee T. B. Marshall T. P. Noe J. W. Proffitt J. M. Shea P. R. Simmons K. Smith NSRB Support P. D. Swafford E. J. Vigluicci EDMS I:license/lers/2013/LER 327/2012-001.docx
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 10/31/2013 (10-2010)
, the NRC may sfor each block) not conduct or sponsor, and a person is not required to respond to, the digits/characters information collection.
- 3. PAGE Sequoyah Nuclear Plant (SQN) Unit 1 05000327 1 OF 9
- 4. TITLE:
Unanalyzed Condition Affecting Essential Raw Cooling Water System due to External Flooding
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED SEQUENTIAL REV MONTH DAY YEAR FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR NUMBER NO.
SQN Unit 2 05000328 FACILITY NAME DOCKET NUMBER 12 12 2012 2012 -
001 00 02 08 2013
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply) 1 El 20.2201(b)
El 20.2203(a)(3)(i) 50.73(a)(2)(i)(C)
E] 50.73(a)(2)(vii)
El 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)
M 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)
El 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL El 20.2203(a)(2)(ii)
El 50.36(c)(1)(ii)(A)
El 50.73(a)(2)(iv)(A)
El 50.73(a)(2)(x) 100 El 20.2203(a)(2)(iii)
El 50.36(c)(2)
M 50.73(a)(2)(v)(A)
El 73.71 (a)(4)
El 20.2203(a)(2)(iv)
El 50.46(a)(3)(ii)
Z 50.73(a)(2)(v)(B)
El 73.71(a)(5)
El 20.2203(a)(2)(v)
El 50.73(a)(2)(i)(A)
El 50.73(a)(2)(v)(C)
[] OTHER 20.2203(a)(2)(vi) 50.73(a)(2)(i)(B) 50.73(a)(2)(v)(D)
Specify in Abstract below or in C.
Dates of Major Occurrences:
1971 April 26, 1974 January 24, 1978 October 10, 1980 January 15, 1985 The initial design criteria for electrical cables in the MNWYs penetrating into the ERCW Pumping Station included a testing requirement to fill the MNWYs with water and be pressurized. To perform the test, each of the MNWY covers needed to be watertight.
The 1971 design criterion for electrical cables leading to the ERCW Pumping Station was revised to remove the initial testing requirement. The revised design change stated the ERCW Pumping Station will remain dry during a flood but, did not identify flood barriers or provide details to maintain the ERCW Pumping Station dry.
As-Constructed drawings of ERCW Pumping Station were issued. However, the documentation neither provided clear information about ERCW Pumping Station design basis flood (DBF) boundaries nor provided reference that validated potential flood boundaries were adequate for a DBF. The documentation did show the original plant design had CHICO A, a leak sealing compound, in electrical conduits in MNWY-33 but, no analysis supports CHICO A as a suitable flood barrier.
A revision to the conduit and grounding drawings included a reference to generic fire penetration drawings for sealing instructions because of a similar detail for EYS sealing fittings with CHICO A compounds. As a result, a loss of configuration control occurred because the fire protection drawings contained sealing details that did not pertain to flood barriers.
A revision to fire protection drawings allowed for use of Dow Corning room temperature vulcanizing (RTV) compound as a substitute for CHICO A in fire stop penetrations. Limited testing of the Dow Corning RTV was performed in 1980 for a different application. There is no documentation supporting adherence to the vendor recommended application of Dow Corning RTV for MNWY-33.
July 11, 1986 June 17, 1991 July 7, 1995 August 13, 2002 September 16, 2012 November 15, 2012 November 19, 2012 December 3, 2012 A revision to the fire protection drawings included a note to discuss watertight conduit and penetration seals. Testing performed using the Dow Corning RTV in blank electrical conduits was performed but, does not provide satisfactory results for use as a watertight seal (it leaked).
SQN implemented a design modification to remove the MNWY watertight cover and install dipstick holes to determine if the MNWY had flooded. Since no requirements for periodic leak testing were identified, and it was presumed that the watertight cover seals no longer performed a function, the MNWY cover seals were removed. This left the electrical conduit seals as the only barrier against a flood above plant grade.
A design modification for electrical conduits allowed the use of 'C' condulet with RTV in place of the EYS sealing fittings with RTV. The design modification did not contain sufficient detail for DBF considerations.
An administrative change to the conduit and grounding drawing denoted that EYS sealing fitting were not required and 'C' condulet could be substituted for electrical conduits.
The NTTF walkdown identified a potential leak path into the ERCW Pumping Station via electrical conduits.
An FE was conducted for the potential leak path into the ERCW Pumping Station via electrical conduits.
A temporary modification to install sump pumps into the ERCW Pumping Station is performed.
A design modification to insert conduit seals in MNWY-33 electrical conduits is developed for implementation.
December 12, 2012 December 15, 2012 January 4, 2013 The steel MNWY cover and concrete missile shield at MNWY-33 is removed for inspection and documentation of as found conditions. Upon inspection of MNWY-33, TVA determined that SQN Units 1 and 2 were at risk of flooding into the ERCW Pumping Station during a flood above plant grade as a result of electrical conduit penetration seals not being filled with material required to make the ERCW Pumping Station watertight. Subsequently, an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> notification was made to the NRC.
The temporary modification for the ERCW Pumping Station is revised to add larger capacity sump pumps based on a revision to the in-leakage calculation. The installation of the sump pumps was completed.
The FE for potential leak path into the ERCW Pumping Station via electrical conduits is revised as a result of the as found inspection results.
D.
Other Systems or Secondary Functions Affected
No other systems or secondary functions were affected by this event.
E.
Method of Discovery
The condition of potential water in-leakage into the ERCW was identified by TVA during the NTTF walkdown.
F.
Operator Actions
Operations issued a Standing Order that provides guidance for operation of the ERCW temporary sump pumps upon meeting entry conditions for Abnormal Operating Procedure (AOP)-N.03, External Flooding.
G.
Safety System Responses:
No safety systems activation occurred.
III.
CAUSE OF THE EVENT
A.
Root Cause:
The root cause analysis determined that existing documentation including licensing documents and configuration controlled drawings for the ERCW Pumping Station do not contain sufficient information to identify flood barriers. SQN design criteria for Flood Protection, states that the ERCW Pumping Station shall remain dry, but does not clearly identify what is credited as flood barriers. Further, configuration controlled drawings do not indicate that the conduit and penetration seals are performing the function of a flood barrier, only that these are watertight.
B. Contributing Factor:
Inadequate configuration control for DBF protection existed as noted by several revisions to configuration controlled drawings which led to an inadequate seal applied to conduits in MNWY-33.
Maintenance practices related to flooding issues were not sensitive to the requirements for maintaining adequate flood barriers during a flooding event.
IV.
ANALYSIS OF THE EVENT
The ERCW system is safety related and is designed to supply cooling water to various essential heat loads in both the primary and secondary portions of each unit. Provisions are made to ensure a continuous flow of cooling water to those systems and components necessary for plant safety during either normal operation or under accident conditions; including external flooding events. The ERCW system is designed to continue operation during the. post-flood condition. The availability of water for the most demanding condition on the ERCW system is based on the following events occurring simultaneously: loss of offsite power, loss of downstream dam, loss of two diesel generator units serving the same power train, and a design basis earthquake.
The ERCW Pumping Station is designed to remain fully functional for floods up to the Probable Maximum Flood (PMF) including wind-wave run-up. The deck elevation (elevation 720 feet) is below the PMF plus wind wave run-up, but is protected from flooding by outside walls. The lower elevations of the ERCW Pumping Station are intended to be watertight. The lower floors of the ERCW Pumping Station are separated into three bays. One bay is for all of the B-train ERCW components. There are two bays for the A-train ERCW components, each has essentially one-half of the required ERCW components.
Based on a review of the supporting documents, it was determined that the electrical conduit penetration seals were meant to be the flood barrier. However, there was no clear identification of the flood barriers and their requirements. The associated maintenance activities on the flood barriers were performed using the fire penetration drawing, which is what the conduit and grounding drawing referenced.
The EYS sealing fittings with CHICO A sealing compound were originally installed in MNWY-33 and they acted as the barrier against flooding, but the lack of documented design basis for flooding barriers since initial construction eventually led to the replacement of some of the EYS sealing fittings with a less than adequate seal. A plant modification will install electrical conduit seals that have been tested to withstand the head pressure that could be exerted during a flood.
V.
ASSESSMENT OF SAFETY CONSEQUENCES
Based on the above information, a potential for a reduction in the defense-in-depth to nuclear safety existed. As a result, this event could potentially have adversely affected the health and safety of plant personnel or the general public had an actual flooding event occurred. No flooding event occurred or is pending.
The ERCW Pumping Station is designed to remain fully functional for floods up to the DBF. AOP-N.03, External Flooding, provides the necessary actions to mitigate the effects on plant operations during probable maximum external flood conditions.
Interim measures installed temporary sump pumps in the ERCW Pumping Station to remove excess water in order to keep equipment operable during flooding conditions. The FE calculates both the leak rate into the ERCW Pumping Station and pumping capacity of the temporary sump pumps. The FE determined that one bay of ERCW systems would be inundated based on the existing seals. One of A-train bays (two bays exist) is required for safe shutdown during a DBF. For the time prior to the installation of the temporary pumps, there is no supporting evidence to conclude that the ERCW system could have performed its design function during a flood above plant grade.
In addition to level considerations, plant flood preparations will cope with the "fastest rising" flood which is the calculated flood that can exceed plant grade with the shortest prediction notice. Reservoir levels for large floods in the Tennessee Valley can be predicted well in advance.
A minimum of 27 hours3.125e-4 days <br />0.0075 hours <br />4.464286e-5 weeks <br />1.02735e-5 months <br />, divided into two stages, is provided for safe plant shutdown by use of this prediction capability. Stage I, a minimum of 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> long, will commence upon a prediction that flood-producing conditions might develop. Stage II, a minimum of 17 hours1.967593e-4 days <br />0.00472 hours <br />2.810847e-5 weeks <br />6.4685e-6 months <br /> long, will commence on a confirmed estimate that conditions will provide a flood. This two-stage scheme is designed to prevent excessive economic loss in case a potential flood does not fully develop.
The estimated probability is less than 2.6E-3 that a Stage I flood warning will be issued during the 40-year life of the plant. The estimated probability is less than 1.OE-3 that shutdown will need to continue into Stage II during plant life.
Deterministically, the risk of a maximum flooding event is low because of the low probability of a PMF, the ample warning time, the development of the event over an extended period of time, and the additional resources that would be available to perform mitigating actions.
VI.
CORRECTIVE ACTIONS
A.
Immediate Corrective Actions
The steel MNWY cover was opened to assess conditions affecting the ERCW Pumping Station was performed. Temporary modification installed sump pumps in ERCW Pumping Station. Installation of qualified conduit seals is in progress.
B. Corrective Actions to Prevent Recurrence:
The following corrective actions to prevent recurrence were identified in the root cause analysis and are being tracked in accordance with the SQN Corrective Action Program.
- 1. SQN will issue a design basis document that will include, but not limited to, the following: identify SSC's which provide external flooding protection for the Emergency Diesel Generator Building and ERCW Pumping Station, ensure adequacy of identified barriers, design requirements / regulatory and licensing requirements, reference AOP-N.03, reference drawing series and test data, and develop an inspection program for flood barriers.
- 2. An exterior flood barrier drawing series will be issued to identify the exterior flood boundaries and contain seal details. Associated drawings will be revised as applicable.
VII.
ADDITIONAL INFORMATION
A.
Failed Components:
None B.
Previous LERs on Similar Events:
A review of previous reportable events for the past three years did not identify any
similar events
C. Additional Information
The corrective action document for this report is Problem Evaluation Report (PER) 655763 (Root Cause Evaluation).
D.
Safety System Functional Failure:
The ERCW system would not have been available to perform its function.
E.
Unplanned Scram with Complications:
This event did not result in an unplanned scram with complications.
VIII.
COMMITMENTS
None