| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
05/17/2007 - 05/18/2007 ** EVENT NUMBERS ** |
 | Power Reactor | Event Number: 43353 | Facility: POINT BEACH
Region: 3 State: WI
Unit: [1] [2] [ ]
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: RYAN RODE
HQ OPS Officer: JEFF ROTTON | Notification Date: 05/09/2007
Notification Time: 19:33 [ET]
Event Date: 05/09/2007
Event Time: 16:23 [CDT]
Last Update Date: 05/17/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
| Person (Organization):
PATTY PELKE (R3)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 100 | Power Operation | 100 | Power Operation | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text UNANALYZED CONDITION DUE TO IDENTIFIED NON COMPLIANT FIRE PROTECTION MANUAL OPERATOR ACTIONS
"During performance of NFPA-805 Transition Project Task SUP-1, 'Manual Action Compliance,' it was determined there were 11 non-compliant manual operator actions that were being performed to achieve and maintain hot safe shutdown in Fire Area A06 (1B32 area). These manual actions were being performed in an Appendix R Section III.G.1/G.2 fire area, however, they do not meet the criteria for allowable manual actions specified in RIS 2006-10, 'Regulatory Expectations with Appendix R Paragraph III.G.2 Operator Manual Actions.'
"The discovery of these non-compliant manual actions is being reported as an unanalyzed condition as defined by 10 CFR 50.72(b)(3)(ii). Appropriate compensatory measures have been established for Fire Area A06 via initiation of hourly fire rounds. An extent of condition review has been initiated that will encompass the remainder of the safe shutdown areas in both Point Beach Nuclear Plant (PBNP) units. The results of the extent of condition will be documented in the site's corrective action program with compensatory measures being established as appropriate. The 60-day licensee event report, submitted to the Commission in accordance with 10 CFR 50.73(a)(2)ii), will provide the results of the manual action compliance review and follow-up corrective actions.
"The PBNP Resident Inspector has been notified of this event."
* * * UPDATE 1735 EDT ON 05/15/07 FROM ERIC SCHULTZ TO S. SANDIN * * *
"This is an update to EN 43353 submitted at 19:33 EDT on 05/09/07:
"During performance of NFPA-805 Transition Project Task SUP-1, 'Manual Action Compliance,' it was determined that non-compliant manual operator actions are credited to achieve and maintain hot safe shutdown for a fire. The following actions were identified during the extent of condition reviews conducted subsequent to EN 43353 report.
# Non-Compliant Actions
1 - Fire Area A03, 1P-2C CVCS Charging Pump Cubicle
1 - Fire Area A04, 1P-2B CVCS Charging Pump Cubicle
1 - Fire Area A05, 1P-2A CVCS Charging Pump Cubicle
6 - Fire Area A07, Chemical Drain, Laundry Tank and Reactor Coolant Pump Seal Filter Room
5 - Fire Area A08, HVAC Equipment Room & Pipeway No. 1 Valve Gallery Area
"These manual actions are credited for safe shutdown in an Appendix R Section III.G.1/G.2 fire area, however, they do not meet the criteria for allowable manual actions specified in RIS 2006-10, 'Regulatory Expectations with Appendix R Paragraph III.G.2 Operator Manual Actions.'
"The discovery of these non-compliant manual actions is being reported as an unanalyzed condition as defined by 10 CFR 50.72(b)(3)(ii). Appropriate compensatory measures have been established for Fire Areas A03, A04, A05, A07 and A08 via initiation of hourly fire rounds. An extent of condition review is continuing that will encompass the remainder of the safe shutdown areas in both Point Beach Nuclear Plant (PBNP) units.
"The PBNP Resident Inspector has been notified of this event." Notified R3DO (Mark Ring).
* * UPDATE BY HALL TO KOZAL ON 5/16/07 AT 1737 * * *
"This is an update to EN 43353 submitted at 19:33 EDT on 05/09/07:
"During performance of NFPA-805 Transition Project Task SUP-I, 'Manual Action Compliance,' it was determined that the following non-compliant manual operator actions are credited to achieve and maintain not safe shutdown for a fire. These actions were identified during the extent of condition reviews for the above referenced report
[The following non-compliant actions were identified:]
"5 [actions for] Fire Area A01, Primary Auxiliary Building El. 44'& 66' (Except FX237)
5 [actions for] Fire Area A01-G, Unit 1 Fa�ade
5 [actions for] Fire Area A01-H, Unit 2 Fa�ade
3 [actions for] Fire Area A10, Radioactive Gas Treatment Area
3 [actions for] Fire Area A11, Pipeway No. 4 Valve Gallery
1 [actions for] Fire Area Al 2, 2P2C CVCS Charging Pump Room
1 [actions for] Fire Area A13, 2P2B CVCS Charging Pump Room
1 [actions for] Fire Area A14, 2P2A CVCS Charging Pump Room
12 [actions for] Fire Area A15, 2B32 Motor Control Center Area
21 [actions for] Fire Area A23N, North Side of Auxiliary Feedwater Pump Room
19 (actions for] Fire Area A23S, South Side of Auxiliary Feedwater Pump Room
8 [actions for] Fire Area A25, D06 Battery Room
9 [actions for] Fire Area A26, D05 Battery Room
7 [actions for] Fire Area A27, G01, Diesel Generator Room
7 [actions for] Fire Area A28, G02 Diesel Generator Room
1 [actions for] Fire Area A29, Air Compressor Room
1 [actions for] Fire Area A61, P206A & P207A Fuel Oil Pump Room
7 [actions for] Fire Area A71, Diesel Generator Building, Train B Areas"
The licensee notified the NRC Resident Inspector. Notified R3DO (Ring).
* * * UPDATE BY RODE TO MCLEAN/KOZAL ON 5/17/07 AT 1815 * * *
"During performance of NFPA-805 Transition Project Task SUP-1, 'Manual Action Compliance,' it was determined that the following non-compliant manual operator actions are credited to achieve and maintain hot safe shutdown for a fire. These actions were identified during the extent of condition reviews for the above referenced report.
[The following non-compliant actions were identified:]
28 Fire Area A01- A, Primary Auxiliary Building, EL. 8' & Below
18 Fire Area A02, Containment Spray / Safety Injection Pump Room
11 Fire Area A01-CN, Primary Auxiliary Building, EL 26' South Wing
10 Fire Area A01-CS, Primary Auxiliary Building, EL 26' South Wing
9 Fire Area A16, D106 Battery Room
9 Fire Area A17, D04 Electrical Equipment Room
9 Fire Area A18, DO3 Electrical Equipment Room
8 Fire Area A19, D105 Battery Room
16 Fire Area A01-E,Turbine Building & South Service Building
1 Fire Area A01-F, Yard Area
1 Fire Area A54, D305 Swing Battery & D301 Charger Rooms
5 Fire Area A36, Unit 1 Containment Area
5 Fire Area A46, Unit 2 Containment Area
7 Fire Area A68, Train B East Duct Bank & Manholes
2 Fire Area A70, Train A West Duct Bank & Manholes"
The licensee notified the NRC Resident Inspector.
Notified R3DO (Ring) |
| Power Reactor | Event Number: 43363 | Facility: PERRY
Region: 3 State: OH
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: ROBERT KIDDER
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 05/15/2007
Notification Time: 01:53 [ET]
Event Date: 05/15/2007
Event Time: 00:58 [EDT]
Last Update Date: 05/17/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
| Person (Organization):
MARK RING (R3)
ELMO COLLINS (NRR)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | A/R | Y | 30 | Power Operation | 0 | Hot Shutdown | Event Text REACTOR SCRAM DURING TESTING
"An automatic reactor scram occurred due to lowering reactor water level. Digital feedwater tuning activities were in progress at the time of the scram. All systems functioned as designed. The reactor water level has been restored to normal level band. The plant is stable in Hot Shutdown. There were no ECCS injections."
At the time of the scram, the feedwater pump was in manual control for feedwater tuning. When water level started going down quickly, the operator was not able to restore sufficient feedwater flow before the level 3 (water level low) actuation. All control rods fully inserted on the scram. No valves repositioned and no safety or relief valves lifted after the scram. Reactor water level is being maintained with the motor feed pump and decay heat is being removed to the main condenser. The plant is in the normal shutdown electrical lineup. Reactor pressure is 509 psi and stable.
The licensee notified the NRC Resident Inspector.
* * * UPDATE FROM FREDERICK SMITH TO FANGIE JONES ON 05/17/07 AT 1301 * * *
"This call is to clarify information provided in notification Event Number 43363 made by the Perry Nuclear Power Plant on May 15, 2007. The second paragraph, fourth sentence of the notification states: 'No valves repositioned and no safety or relief valves lifted after the scram.' The intent of the portion of the sentence 'No valves repositioned' was supposed to be in reference to the reporting requirement in 10 CFR 50.72(b)(3)(iv) to report any event or condition that results in valid actuation of general containment isolation signals affecting containment isolation valves in more than one system or multiple main steam isolation valves (MSIVs).
"The event on May 15, 2007, did not meet the 'containment isolation valves in more than one system / MSIVs criterion', however, subsequent review of the event identified that Residual Heat Removal 'B' Heat Exchanger Second Vent to Suppression Pool Containment Isolation Valve 1E12-F073B, closed, as designed, in response to the reactor coolant level 3 (water level low) condition that was present during the event. No additional reporting criteria have been identified and this update has been provided to clarify the earlier statement.
"The NRC Resident Inspector has been notified."
Notified R3 RDO, (Ring), and NRR EO, (Ross Lee). |
| Power Reactor | Event Number: 43367 | Facility: INDIAN POINT
Region: 1 State: NY
Unit: [2] [3] [ ]
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: JOHN WELLS
HQ OPS Officer: JEFF ROTTON | Notification Date: 05/16/2007
Notification Time: 20:08 [ET]
Event Date: 05/16/2007
Event Time: 16:55 [EDT]
Last Update Date: 05/17/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
NEIL PERRY (R1)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | | 3 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text LOSS OF 26 EMERGENCY SIRENS DUE TO SEVERE WEATHER
"Due to severe weather storms in the area surrounding Indian Point Energy Center, 26 of the 156 emergency sirens have been out of service as of 1655 hours on 5/16/07 due to either loss of local AC power (24 sirens) or communications problem (2 sirens). 15 of the 26 sirens are in Rockland County; the remaining 11 sirens are in Westchester County. Sirens in Orange and Putnam counties were unaffected. Rockland and Westchester Counties have been notified and route alerting is available as an alternate means of public notification. Additionally, a high speed telephone notification system is available for public notification by the counties. Contact of the local utilities has been initiated to request power restoration to the areas associated with the 24 effected sirens; the communication problems with the remaining 2 sirens are under investigation."
The licensee notified the NRC Resident Inspector, New York State Public Service Commission, and Rockland, Westchester, Putnam and Orange counties.
* * * UPDATE PROVIDED BY JOHN WELLS TO JEFF ROTTON AT 0318 EDT ON 05/17/07 * * *
"Update on status of report on siren status. As of this time only 12 sirens remain out of service and this is below the 16 siren reportability requirement. Breakdown of siren outages is as follows: Rockland County - 2 sirens with power issues only, and Westchester county - 10 sirens out of service of which 6 are due to power and 4 due to communications issues."
The licensee will be notifying the NRC Resident Inspector, New York State Public Service Commission, and Rockland, Westchester, Putnam and Orange counties.
R1DO (Perry) notified. |
| Power Reactor | Event Number: 43368 | Facility: HOPE CREEK
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: BERNARD LITKETT
HQ OPS Officer: JASON KOZAL | Notification Date: 05/17/2007
Notification Time: 14:07 [ET]
Event Date: 05/17/2007
Event Time: 13:40 [EDT]
Last Update Date: 05/17/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
NEIL PERRY (R1)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text OFFSITE NOTIFICATION DUE TO FAILED EMISSIONS TEST
"I am calling you to provide a notification of a potentially failed air emission test on an auxiliary boiler. There is absolutely no evidence to suggest that any emissions from our boilers caused any harm to human health, welfare, or the environment. The emissions are not continuing and there is no assistance required or requested. The statute requires I provide this notification to assert an affirmative defense or a rescission as appropriate. The New Jersey Department of Environmental Protection Hotline was called to report this, Case number 07-0517-134537, operator 27.
"During the start-up tuning and testing of our new auxiliary boilers, it appears that a malfunction of equipment during testing resulted in inconclusive test results for NOx loading for our #1 Boiler. For the testing runs, the measured volumetric stack flows were significantly higher than the stoichiometrically calculated stack flows based on fuel flow measurements.
"While we are still investigating this discrepancy, we preliminarily believe that it was the result of either equipment malfunction, performance of necessary equipment maintenance and equipment start-up and shutdown."
The licensee has notified the State (DEP) and will be notifying the NRC Resident Inspector. |
| Power Reactor | Event Number: 43369 | Facility: NINE MILE POINT
Region: 1 State: NY
Unit: [1] [ ] [ ]
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: MATTHEW MINNICK
HQ OPS Officer: GERRY WAIG | Notification Date: 05/17/2007
Notification Time: 20:23 [ET]
Event Date: 05/17/2007
Event Time: 12:30 [EDT]
Last Update Date: 05/17/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
| Person (Organization):
NEIL PERRY (R1)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown | Event Text DEGRADED CONDITION - DEGRADATION OF PRINCIPAL SAFETY BARRIER
"Under 10CFR50.72 (b)(3)(ii)(A), the following event has been determined to be reportable. This section concerns the condition of the nuclear power plant, including its principal safety barriers, being seriously degraded. This criteria was determined to apply to material problems that cause abnormal degradation of or stress upon a principal safety barrier (in this case, Reactor Coolant System).
"On 5/17/07, a Nine Mile Point Unit 1 shutdown was in progress for forced outage inspection and repairs of the Turbine Lube Oil system. Prior to the shutdown, a discrepancy was being experienced between Reactor level readings from channel 11 and 12 Reactor Level columns. A step change increase of 2 inches of Reactor level had occurred on May 6th, 2007 on Reactor Level column 12. This change was coincident with an increase of 18 [degrees] F of the reference leg and 2 [degrees] F decrease of the variable leg. The level difference was then 5 inches with a Technical Specification limit of 6 inches based on current Drywell temperature. The condition was documented in the Corrective Action Program, compensatory actions were taken, and an Integrated Response Team was formed to investigate and determine the cause. Calculations by engineering determined a leak of 4 drops per minute could explain the observed indications.
"During the initial drywell entry a visual examination was performed on the reference leg instrumentation line associated with Reactor Level Column 12. The piping was visually examined for any evidence of leakage. The exam was performed from the bottom of the condensing pot piping to the drywell shell penetration. The examination revealed a wet area at the bottom of a 1.0 inch 90 degree pipe elbow at an associated socket weld. The weld had one drop approximately 1.0 inch from the toe of the welds on the bottom of the pipe. The drop was wiped away with a leather gloved hand, which did show evidence of leakage. After waiting approx. 15 minutes, no additional leakage was observed. Reactor pressure had been lowered to approximately 400 psig at the time of the inspection due to the Reactor shutdown in progress. The piping, welds and Reactor level column above were closely examined and no other wetness or evidence of leakage was found. Also an exam was performed below pipe weld 012 (surrounding areas) and again no evidence of leakage could be found. No staining or other discoloration could be seen. The observations were documented in the Corrective Action Program."
The licensee also provided the following information:
Location of the Leak: 12 Yarway Reactor Level Reference Leg
Leak Rate: 1 drop per minute
T.S. Limits: 5 gallons per minute
Sudden or Long-term Development: Sudden
Leak Start Date: 5-06-2007
Time: 08:10 a.m. EDT
Coolant Activity: 2.02 E-3 microcuries/ml
Secondary: N/A
List of Safety Related Equipment Not Operational: None
The licensee has notified the NRC Resident Inspector. |
| General Information or Other | Event Number: 43370 | Rep Org: VARFLEX CORPORATION
Licensee: VARFLEX CORPORATION
Region: 1
City: ROME State: NY
County:
License #:
Agreement: Y
Docket:
NRC Notified By: WARREN WILLIAMS
HQ OPS Officer: JASON KOZAL | Notification Date: 05/18/2007
Notification Time: 11:07 [ET]
Event Date: 05/18/2007
Event Time: [EDT]
Last Update Date: 05/18/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
| Person (Organization):
NEIL PERRY (R1)
CHRISTINE LIPA (R3)
PART 21 GROUP ()
| Event Text ELECTRICAL INSULATING SLEEVING HAS NOT BEEN SUBMITTED FOR UL FLAMMABILITY COMPLIANCE
The licensee provided the following information via facsimile:
"Since 1999, our customer, Transco Products Inc., Chicago IL, has purchased items of electrical insulating sleeving (natural Varglas Silicone Resin 500 Sleeving Class H-A-1) in various sizes from us with the requirements that they be UL recognized for 200 degrees C, 600 volt service and that they comply with ULs VW-1 flammability requirements to be accomplished by a Certificate of Conformance attesting to those points.
"Although this sleeving's UL recognition for 200 degrees C, 600 volt service is covered under UL File E63450, and is not recognized for complying with the type VW-1 flammability classification under File E63450, the material was certified to Transco's purchase orders.
"Transco's customer is Exelon Corporation, Chicago, IL.
"However, although the above product has not been submitted to, nor has it been recognized by, UL for compliance to its VW-1 flammability requirements, Varflex tests, done in complete accordance with ULs VW-1 Test procedures, indicate the product does qualify for UL recognition and, therefore, does not create a substantial safety hazard.
"UL recognition will be pursued." | |