09-20-2004 | determined that the Kewaunee Nuclear Power Plant had missed a surveillance required by Technical Specifications (TS). Specifically, the requirements of TS, Sections 4.13.b and e, were not met. Section 4.13, "Radioactive Materials Sources," in part, requires sources be leak tested in accordance with TS, and sources in storage, not being used and exempt from periodic leak testing shall have a current leak test prior to use or transfer to another licensee.
Contrary to TS and based on review of plant records from 1973 through 2004, leak tests were not performed on 13 new in-core detector sources prior to being put into use, or shipped to another licensed facility. The cause for the missed surveillance was inadequate procedural guidance providing instructions to have required leak tests performed on in-core detectors. Procedure changes to the applicable procedures have been initiated to ensure required leak tests are performed in the future. NMC personnel will also contact licensees that received any in-core detectors that had not been leak tested to determine the scope of any additional corrective action needed to ensure regulatory requirement compliance.
The safety significance of failing to complete leak tests required by TS is minimal. Historical radiological survey data, which includes the areas where the detectors may have been stored, or placed for processing, show no evidence of byproduct material expected from a leaking in-core detector. |
---|
FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (6 PAGE (3) Kewaunee Nuclear Power Plant 05000305 YEAR I 2004 — 002 — 00 _
Event Description:
On July 21, 2004, while the plant was operating at full power, Nuclear Management Company (NMC) personnel determined that the Kewaunee Nuclear Power Plant (KNPP) had missed a surveillande required by Technical Specifications (TS). Specifically, the requirements of TS, Sections 4.13.b and e, were not met.
Section 4.13, "Radioactive Materials Sources," subsections b and e, read as follows:
b. Sources which contain by-product material that exceeds the quantities listed in 10 CFR 30.71, Schedule B, and all other sources containing > 0.1 microcuries shall be leak tested in accordance with this TS.
e. Sources specified by TS 4.13.b which are in storage and not being used are exempt from the testing of TS 4.13.d. Prior to use or transfer to another licensee of such a source, the leakage test of TS 4.13.d shall be current.
Contrary to the TS, and based on a review of plant records from 1973 through 2004, leak tests were found not to have been performed on 13 detectors [DET] with greater than 0.1 microcuries (uCi) activity, prior to being put into use or shipped to another licensed facility.
On January 30, 2004, a Corrective Action Program (CAP) document #19783 was issued at KNPP. The Cap was issued based on an industry operating experience (OE) event; a Traversing Incore Probe (TIP) detector was transferred between two licensee facilities without leak test documentation. The CAP was written to perform a review of this OE item for applicability at KNPP. The initial evaluation, performed by the plant Health Physics (HP) Group, questioned the clarity and understanding of TS 4.13, related to fission detectors. There was a question raised on the mechanism used at KNPP to prompt the initiation of leakage testing of fission detectors prior to transfer or prior to installing them in the reactor core. The plant warehouse process requests suppliers of radioactive material to mark packages to notify HP upon receipt. This would not necessarily prompt HP to do a leak test, but rather to perform a general package survey.
The Reactor Engineering (RE) Group was assigned to perform an evaluation of the issue in accordance with corrective action OTH 15150, a sub-task of CAP 19783. It was subsequently determined that required leak tests of in-core fission chamber detectors, prior to being put into use or subjected to core flux, were not performed per TS 4.13. This was determined by reviewing records of Surveillance Procedure (SP)80-005 (Radioactive Source Inventory and Leak Testing Requirements) for the past five years.
Work Orders (WOs) for two replacement in-core detectors were reviewed under the OE CAP. No documentation was found to indicate that a leakage test was performed on the detectors. The evaluation efforts also did not indicate any missed TS leak tests (surveillance) regarding transfer of in-core detectors to another licensee.
HP performed a review of procedure SP-80-005. Two steps were identified that reference the need to leak test sources in storage prior to use or transfer to another licensee. Also, Technical Specification 4.13 is listed in the reference section.
A review of past plant documentation revealed a similar issue captured in the former KNPP corrective action program in January 1994 as incident report (IR)94-017. This report discussed in-core detectors not being FACILITY NAME (1)� DOCKET NUMBER (2) LER NUMBER (6 PAGE (3) leak tested prior to being put into use. The correct conclusion from IR 94.017 was that the in-core detectors evaluated at the time were less than 0.1 uCi. Therefore, no missed surveillance occurred at that time in that the requirements of the TS did not apply.
A review was conducted of purchase order receipts as early as 1974. According to these records, 59 in-core detectors were identified as being received. 46 of the in-core detectors were less than 0.1 uCi. Three of the receipts in 1984, 1985, and 1992 list the curie content of 13 in-core detectors as 0.25 uCi each.
There are currently three in-core detectors stored in the warehouse:
■ M3222, received on September 7, 1993, curie content unknown.
■ 95S01151, received on December 18, 1995, curie content 0.37 uCi.
■ 032205, received on January 14, 2004, curie content 0.31 uCi. This detector has been leak tested, and no leakage was detected.
A review of the Special Nuclear Materials (SNM) Records Ledger maintained by Reactor Engineering was conducted. The data indicated that KNPP had received 79 in-core detectors since 1974. Comparing the receipt information against the SNM Records Ledger the following was identified:
- 1984 — The two detectors received with 0.25 uCi activity each, were put into use.
= 1985 — The eight detectors received with 0.25 uCi activity each, were put into use.
2 1992 — The three detectors received with 0.25 uCi activity each, were shipped to another licensed facility.
A review of SP 80-005 records from 1973 through 2004 found no leak tests performed on the in-core detectors.
Based on the above investigation and evaluation, it was verified on July 21, 2004 that 13 in-core detectors with greater than 0.1 uCi activity had either been put into use or transferred to another licensee without TS required leak tests having been performed.
An extent-of-condition review was performed relative to leak testing other radioactive sources at KNPP. This review took into account other fission chambers, calibration sources, and check sources. Three ex-core detectors were received in 1991. All three had material curie content levels greater than 0.1 uCI, they were appropriately leak tested, and no leakage was detected.
Event Analysis:
This event is reportable in accordance with 10CFR50.73 (a)(2)(i)(B); Any operation or condition which was prohibited by the plant's Technical Specifications.
FACILITYNAME (1) DOCKET NUMBER (2) LER NUMBER (6 PAGE (3) 2004 — 002 — 00 _
Safety Significance:
The basis for the required surveillance discussed in the KNPP Technical Specifications, is the postulated ingestion or inhalation of source material resulting in whole body or organ irradiation. The in-core detectors contain uranium, which emits an alpha particle upon decay. Historically, area radiological surveys throughout the plant have detected no alpha contamination. Area surveys include the plant warehouse, where the in-core detectors are stored, and the area of the seal [SEAL] table in the reactor building containment [NH] where the detectors are installed. Therefore, the potential of ingestion or inhalation or source material having occurred is not likely. Consequently, the safety significance of this occurrence is minimal.
Cause:
The cause for the missed surveillance was inadequate receiving process and controlling procedure guidance.
Existing instructions to have leak tests performed on in-core detectors prior to use or transfer to another licensed facility were not sufficiently comprehensive to ensure TS compliance.
Corrective Actions:
1. Actions that have been completed:
a. A temporary procedure change was made to procedure RE-05 (In-core Instrumentation Periodic Hardware Maintenance). A step was added to ensure in-core detectors are leak tested by Health Physics before being installed.
b. A temporary procedure change was made to procedure RE-24 (Special Nuclear Material Control). A step was added to ensure any non-irradiated fission chamber detector have a leakage test performed before being shipped to another licensee.
c. This issue and associated lessons-learned were presented and discussed in-detail at the June 30, 2004 Radiation Protection group meeting.
d. Instructions were placed in the fission chamber stock requisition request item description section to advise Reactor Engineering, upon receipt of detectors, prior to transferring to another licensee or installing detector in the plant, they must be leak tested per TS 4.13.
2. Actions that will be taken:
a. NMC will contact the licensees that received any in-core detectors with greater than 0.1 uCi that had not been leak tested to determine the scope of any additional corrective actions needed to ensure regulatory compliance.
FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (6 PAGE (3) yEAil SEQUENTIAL REVISION b. Detectors M3222 and 95S01151 in the warehouse will be leak tested prior to being placed into the reactor, or prior to shipment to another location, as applicable.
c. An effectiveness review of the process by which the sources are leak tested per Technical Specification Requirements will be performed by the KNPP Nuclear Oversight organization.
d. Permanent procedure changes consistent with the temporary changes described will be completed.
Previous Similar Events:
None.
|
---|
|
|
| | Reporting criterion |
---|
05000348/LER-2004-001 | | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000333/LER-2004-001 | Inadvertent Actuation of ECCS and EDGs While in Refueling Mode | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000306/LER-2004-001 | | 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000315/LER-2004-001 | Failure To Comply With Technical Specification 3 .7 .5 .1, Control Room Emergency Ventilation System | | 05000301/LER-2004-001 | | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000313/LER-2004-001 | | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000285/LER-2004-001 | Failure To Perform A Leakage Test Due To Lack Of Understanding of Penetration Design | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000271/LER-2004-001 | Main Steam Isolation Valve Leakage Exceeds a Technical Specification Leakage Rate Limit | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000266/LER-2004-001 | | 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded | 05000318/LER-2004-001 | . Reactor Trip Due to Low Steam Generator Water Level After Feed Pump Trip | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000289/LER-2004-001 | | 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000263/LER-2004-001 | | | 05000247/LER-2004-001 | Manual Reactor Trip Due to Oscillating Feedwater Flow and Steam Generator Level with Flow Perturbations Caused by a Degraded Feed Water Regulating Valve | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(iv), System Actuation | 05000244/LER-2004-001 | Gaps in the Control Room Emergency Zone Boundary | | 05000255/LER-2004-001 | | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000364/LER-2004-001 | | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000461/LER-2004-001 | Clinton Power Station 05000461 1 OF 4 | | 05000414/LER-2004-001 | relPowere Vice President A Duke Energy Company Duke Power Catawba Nuclear Station 4800 Concord Rd. / CNO1VP York, SC 29745-9635 803 831 4251 803 831 3221 fax November 9, 2004
U. S. Nuclear Regulatory Commission
ATTENTION: Document Control Desk
Washington, DC 20555-0001
SUBJECT: Duke Energy Corporation
Catawba Nuclear Station Unit 2
Docket No. 50-414
Licensee Event Report 414/04-001 Revision 0
Reactor Coolant System Pressure Boundary Leakage
Due to Small Cracks Found in Steam Generator
Channel Head Bowl Drain Line on 2C & 2D Steam
Generators
Attached please find Licensee Event Report 414/04-001
Revision 0, entitled "Reactor Coolant System Pressure
Boundary Leakage Due to Small Cracks Found in.Steam
Generator Channel Head Bowl Drain Line on 2C & 2D Steam
Generators."
This Licensee Event Report does not contain any regulatory
commitments. Questions regarding this Licensee Event Report
should be directed to R. D. Hart at (803) 831-3622.
Sincerely,
Dhiaa Jamil
Attachment
www.dukepower.corn 00- U.S. Nuclear Reguldhory Commission
November 9, 2004
Page 2
XC: W.D. Travers
U.S. Nuclear Regulatory Commission
Regional Administrator, Region II
Atlanta Federal Center
61 Forsyth St., SW, Suite 23T85
Atlanta, GA 30303
E.F. Guthrie
Senior Resident Inspector (CNS)
U.S. Nuclear Regulatory Commission
Catawba Nuclear Station
S.E. Peters (addressee only)
NRC Project Manager (CNS)
U.S. Nuclear Regulatory Commission
One White Flint North, Mail Stop 10-B3
11555 Rockville Pike
Rockville, MD 20852-2738
NRC FORM 366� U.S. NUCLEAR REGULATORY APPROVED BY OMB: NO. 3150-0104 EXPIRES: 06/30/2007 (6-2004)� COMMISSION Estimated burden per response to comply with this mandatory collection request 50
hours. Reported lessons learned are Incorporated Into the licensing process and fed back
to Industry. Send comments regarding burden estimate to the Records and FOIA/Privacy
Service Branch (T-5 F52), U.S. Nuclear Regulatory Commission, WashinMon, DC 2055
LICENSEE EN/ENT REPORT (LER) 0001, or by Internet e-mail to infocollects@nrc.gov, and to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-10202, (3150-0104). Office of Management(See reverse for required number of and Budget, Washington, DC 20503. If a means used to impose an Information col ectiond( inverse �for each block) does not display a currently valid OMB control number, the NRC may not conduct or sponsor. and a person Is not required to respond o. the Information collection. 1. FACILITY NAME 2. DOCKET NUMBER 3. PAGE Catawba Nuclear Station, Unit 2 050- 00414 1 OF�6 4. TITLE Reactor Coolant System Pressure Boundary Leakage Due to Small Cracks Found in
Steam Generator Channel Head Bowl Drain Line on 2C & 2D Steam Generators | | 05000368/LER-2004-001 | | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000423/LER-2004-001 | | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000334/LER-2004-001 | Control Rod Shutdown Bank Anomaly Causes Entry into Technical Specification 3.0.3 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000413/LER-2004-001 | Gas Accumulation in Centrifugal Charging Pump Suction Piping | 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded | 05000395/LER-2004-001 | Reactor Trip Due to Valve Failure During Forced Shutdown | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown | 05000390/LER-2004-001 | Automatic Reactor Trip Due to a Invalid Turbine Trip Signal (P-4) | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000369/LER-2004-001 | Auxiliary Feedwater System in prohibited condition due to inadequate procedure. | | 05000454/LER-2004-001 | Exelent
Exelon Generation Company, LLCRwww.exeloncorp.com NuclearByron Station 4450 North German Church Road Byron, IL 61010-9794 October 17, 2004 LTR: BYRON 2004-0111 File: 2.01.0700 United States Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Subject:RLicensee Event Report (LER) 454-2004-001-00, "Reactor Containment Fan Coolers Flow Rates Below Technical Specification Requirements Due to Inaccurate Flow Indication" Byron Station, Unit 1
Facility Operating License No. NPF-37
NRC Docket No. STN 50-454
Enclosed is an LER involving the August 17, 2004, event involving low flow conditions discovered in Unit 1 Reactor Containment Fan Coolers for a time period longer than allowed by the Technical Specifications. This event is reportable to the NRC in accordance with 10CFR 50.73 (a)(2)(i)(B), as a condition prohibited by Technical Specifications. Should you have any questions concerning this matter, please contact Mr. William Grundmann, Regulatory Assurance. Manager, at (815) 234-5441, extension 2800. Respectfully, Stephen E. Kuczynski Site Vice President Byron Nuclear Generating Station Attachment LER 454-2004-001-00 cc:RRegional Administrator, Region III, NRC NRC Senior Resident Inspector— Byron Station NRC FORM 366 U.S. NUCLEAR REGULATORY APPROVED BY OMB NO. 3150-0104 EXPIRES 7-31-2004 (7.2001) COMMISSION Estimated burden per response to comply with this mandatory information collection request 50 hours. Reported lessons learned are incorporated into the licensing process and fed back to industry. Send comments regarding burden estimate to the Records Management Branch (T.6 E6), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by Internet e-mail toLICENSEE EVENT REPORT (LER) *I@ nrc.gov, and to the Desk Officer, Office of Informabon and Regulatory Affairs, NEOB:10202 (3150-0104), Office of Management and Budget, Washington, DC 20503. If a means used to impose information collection does not display a currently valid OMB control number, the NRC may not _ conduct or sponsor, and a person is not required to respond to, the information collection. 1 rand ITV NAUP o natuerr An warn q par= . Byron Station, Unit 1 0500454 1 OF 5 4. Reactor Containment Fan Coolers Flow Rates Below Technical Specifications Requirements Due to Inaccurate Flow Indication | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000305/LER-2004-001 | | 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability | 05000336/LER-2004-001 | | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000364/LER-2004-002 | | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000423/LER-2004-002 | | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000237/LER-2004-002 | Dresden Nuclear Power Station Unit 2 05000237 1 of 5 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000261/LER-2004-002 | | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000244/LER-2004-002 | Consolidated Rod Storage Canister Placed in Incorrect Storage Location | | 05000530/LER-2004-002 | Main Turbine Control System Malfunction Results in Automatic Reactor Trip on Low DNBR | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(v), Loss of Safety Function | 05000305/LER-2004-002 | | | 05000247/LER-2004-002 | Manual Reactor Trip Due to Decreasing 23 Steam Generator Level Caused by Feedwater Regulating Valve Closure Due to a De-energized Solenoid Operated Valve from Wiring Failure | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000414/LER-2004-002 | Manual Reactor Trip Initiated Due to Control Rods from Shutdown Bank D Dropping into the Core | | 05000251/LER-2004-002 | AAA | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(iv)(b) | 05000397/LER-2004-002 | | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | 05000346/LER-2004-002 | Reactor Trip During Reactor Trip Breaker Testing Due To Fuse Failure | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000395/LER-2004-002 | Emergency Diesel Generator Start and Load Due to Momentary Fault on Incoming Feed | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000269/LER-2004-002 | eif Powere RON A. JONES Vice President A Duke Energy Company Oconee Nuclear Site Duke Power ONO1VP / 7800 Rochester Highway Seneca, SC 29672 864 885 3158 864 885 3564 fax September 9, 2004
U.S. Nuclear Regulatory Commission
Document Control Desk
Washington, D.C. 20555
Subject: Oconee Nuclear Station
Docket Nos. 50-269,-270, -287
Licensee Event Report 269/2004-02, Revision 1
Problem Investigation Process No.: 0-04-2808
Gentlemen:
Pursuant to 10 CFR 50.73 Sections (a)(1) and (d), attached
is Licensee Event Report 269/2004-02, Revision 1, regarding
a Main Steam Line Break mitigation design/analysis
deficiency which could result in the main and startup
feedwater control valves being technically inoperable for
mitigation of some steam line break scenarios.
This report is being submitted to supplement Revision 0
submitted July 6, 2004. At that time the root cause
investigation and an analysis of the consequences of
potentially exceeding the Environment Qualification (EQ)
envelope curve were still in progress.
This event is being reported in accordance with 10 CFR
50.73 (a)(2)(i)(B) as a condition prohibited by Technical
Specifications, 50.73(a)(2)(ii)(B) as an Unanalyzed
Condition, and 50.73(a)(2)(V)(D) as a potential loss of
safety function for Accident Mitigation. This event is
considered to be of no significance with respect to the
health and safety of the public.
www.dukepower.corn Document Control Desk
Date: September 9, 2004
Page 2
Attachment: Licensee Event Report 269/2004-02, Revision 1
cc: Mr. William D. Travers
Administrator, Region II
U.S. Nuclear Regulatory Commission
61 Forsyth Street, S. W., Suite 23T85
Atlanta, GA 30303
Mr. L. N. Olshan
Project Manager
U.S. Nuclear Regulatory Commission
Office of Nuclear Reactor Regulation
Washington, D.C. 20555
Mr. M. C. Shannon
NRC Senior Resident Inspector
Oconee Nuclear Station
INPO (via E-mail)
NRC FORM 366 U.S. NUCLEAR REGULATORY APPROVED BY OMB NO. 3150-0104 EXPIRES 7-31-2004 (7-2001) COMMISSION Estimated burden per response to comply with this mandatory information collection request: 50 hours. Reported lessons learned are incorporated into the licensing process and fed back to industry. Send comments regarding burden estimate to the Records Management Branch (T-6 E6), U.S. Nuclear Regulatory Commission, Washington. DCLICENSEE EVENT REPORT (LER) 20555-0001, or by Internet e-mail to bpi @nrc.gov, and to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-10202 (3150-0104), Office of Management and(See reverse for required number of Budget, Washington, DC 20503. If a means used to impose information collection doesdigits/characters for each block) not display a currently valid OMB control number, the NRC may not conduct or sponsor, and,1 nnmnn lc not rent Owl to tocnnni-I to the intnrmatinn rntlentinn 1. FACILITY NAME 2. DOCKET NUMBER 3. PAGE Oconee Nuclear Station, Unit 1 050-81 OF 0269 11 4. TITLE Main Steam Line Break Mitigation Design/Analysis Deficiency | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | 05000313/LER-2004-002 | | 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded | 05000271/LER-2004-002 | Special Nuclear Material Inventory Location Discrepancy | | 05000285/LER-2004-002 | Inoperable Diesel Generator for 28 Days Due to Blown Fuse During Shutdown | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000336/LER-2004-002 | | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000311/LER-2004-002 | Failure To Comply With Technical Specifications During Reactor Protection Instrument Calibration . | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000254/LER-2004-002 | Quad Cities Nuclear Power Station Unit 1 05000254 1 of 4 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000263/LER-2004-002 | | | 05000302/LER-2004-002 | Emergency Diesel Generator Inoperable Due To Fuel Oil Header Outlet Check Valve Leaking Past Seat | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
|