05000333/LER-2015-004, Regarding Concurrent Opening of Reactor Building Airlock Doors
| ML15314A800 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 11/06/2015 |
| From: | Brian Sullivan Entergy Nuclear Northeast, Entergy Nuclear Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| JAFP-15-0125 LER 15-004-00 | |
| Download: ML15314A800 (5) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(v), Loss of Safety Function 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) 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)(i)(B), Prohibited by Technical Specifications |
| 3332015004R00 - NRC Website | |
text
Entergy Nuclear Northeast Entergy Nuclear Operations, Inc.
James A. FitzPatnck NPP P0. Box 110 Lycoming, NY 13093 T 1 31D3 3
96 23 F3 j3420480 Brian R. Sullivan Site Vice President JAF JAFP-1 5-0125 November 6, 2015 United States Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555-0001
Subject:
LER: 201 5-004-00, Concurrent Opening of Reactor Building Airlock Doors James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 License No. DPR-59
Dear Sir or Madam:
This report is submitted in accordance with 10 CFR 50.73(a)(2)(v)(C).
There are no commitments contained in this report.
Questions concerning this report may be addressed to Mr. Chris M. Adner, Regulatory Assurance Manager, at (315) 349-6766.
Sincerely, BrSulliva Site Vice President B AS/CMAids Enclosure(s): JAF LEA: 201 5-004-00, Concurrent Opening of Reactor Building Airlock Doors cc:
USNRC, Region 1 USNRC, Project Directorate USNRC, Resident Inspector INPO Records Center (ICES)
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY 0MB: NO. 3150-0104 EXPIRES: 01/3112017 02-2014)
Estimated bvQen per response to comply with this mardatoy collection request: 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> F
Reported essors earned are ircororated nto the licensing precess and ted back to ndust.
Send comments regarding buder estimate to toe FOIA Privacy and tnormat on Collect ons Branch (T-5 P53).
U S. Nuc ear Regu atory Comrrission. Wash rgton. DC 20555-coo or by internet e-ma to tdocoIlects.Resovrce@nrc.gov. and to the Desk Oft.cer. Office of lrtcrmahon and RegLiatory Affars, NEOB-10202. l350D041. Otf.ce of Mar.aenent and Budget. Wasrngton. DC 20503. 1 a means used to imoose an nformahon cc 1
lecton does not dsay a currenty valid 0MB control nLmber, the NRC may rot conduct or sponsor. and a person is not requved to respond to.
the inormahon collechon.
- 3. PAGE James A. FitzPatrick Nuclear Power Plant 05000333 1 OF 4
- 4. TiTLE Concurrent Opening of Reactor Building Airlock Doors
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OThER FACILITIES INVOLVED SEQUENTIAL REV FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR NUMBER NO MONTH DAY YEAR N/A N/A FACILITY NAME DOCKET NUMBER 09 17 2015 2015 004 00 11 06 2015 N/A N/A
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TOTH REQUIREMENTS OF 10 CFR §: (Check all that apply) 20.2201(b) 20.2203(a)(3)(i) 50.73(a)(2)(i)(c) 50.73(a)(2)(vii) 20.2201(d) 20.2203(a)(3)(ii) 50.73(a)(2)(ii)(A)
[] 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) 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)Uv)(A)
El 50.73(a)(2)(x)
El 20.2203(a)(2)(iii)
El 50.36(c)(2)
El 50.73(a)(2)(v)(A)
El 73.71(a)(4) 100 El 20.2203(a)(2)Ov)
El 50.46(a)(3)(ii)
El 50.73(a)(2)(v)(B)
El 73.71 (a)(5)
El 20.2203(a)(2)(v)
El 50.73(a)(2)(i)(A) 50.73(a)(2)(v)(c)
El OTHER El 20.2203(a)(2)(vi)
El 50.73(a)(2)(i)(B)
El 50.73(a)(2)(v)(D)
- 12. LICENSEE CONTACT FOR THIS LER LICENSEE CONTACT TELEPHONE NUMBER (Include Area Code)
Mr. Chris M. Adner, Regulatory Assurance Manager 31 5-349-6766MANU-REPORTABLE I MANU-REPORTABLE
CAUSE
SYSTEM COMPONENT FACTURER TO EPIX j
CAUSE
SYSTEM COMPONENT FACTURER TO EPIX X
NG N/A N/A N
- 14. SUPPLEMENTAL REPORT EXPECTED
- 15. EXPECTED MONTH DAY YEAR SUBMISSION YES (If yes, complete 15. EXPECTED SUBMISSION DATE)
NO DATE ABSTRACT (Limit to 1400 spaces. i.e., approximately 15 single-spaced typewritten lines)
On the morning of September 17, 2015, while operating at 100% power, workers opened doors concurrently when entering a secondary containment access airlock. The individuals involved each closed their respective doors upon encountering this unexpected condition; however, the result was a brief inoperability of secondary containment.
This resulted in an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> reportable event. The Resident Inspector was notified, and an Event Notification was made pursuant to 10 CFR 50.72(b)(3)(v)(C) due to a condition at the time of discovery that prevented the fulfillment of the Secondary Containment safety function (Reference ENS 51405). Following the event, the doors functioned properly, and no deficiencies were noted with either door.
There were no radiological releases associated with this event.
NRC FORM 366 (02-2014)
=
Background===
The Secondary Containment [EIIS identifier: NG] boundary surrounds the primary containment and refueling equipment. The boundary forms a control volume to contain, dilute, and hold up fission products. The Secondary Containment consists of four systems which include the Reactor Building, the Reactor Building Isolation and Control System, the Standby Gas Treatment System, and the Main Stack. Secondary Containment is designed to provide containment for postulated design basis accident scenarios: loss-of-coolant accident and refueling (fuel handling) accident. Since pressure may increase in Secondary Containment relative to the environmental pressure, support systems are required to maintain a differential pressure vacuum such that external atmosphere would leak into containment rather than fission products leak out.
The systems which maintain a differential pressure vacuum inside Secondary Containment include the normal Reactor Building Ventilation and Cooling (RBV) System [VA] (during normal plant operations) and the safety-related Standby Gas Treatment (SBGT) System [BH] for post-accident conditions.
Technical Specification (TS) Surveillance Requirement (SR) 3.6.4.1.3 requires one Secondary Containment access door in each access opening to remain closed. Failure to meet this SR results in the Secondary Containment Limiting Condition for Operation (LCO) not being met, and requires the Secondary Containment to be declared Inoperable.
Event Description
On September 17, 2015, with the James A. FitzPatrick Nuclear Power Plant (JAF) operating at 100 percent power, a member of the Radiation Protection (RP) department and the Nuclear Regulatory Commission (NRC) were about to conduct a walk down of the Reactor Building, and entered the north door of the north Secondary Containment access opening on Elevation 272. A chemistry contractor simultaneously entered the same Secondary Containment access opening via the opposing door on the south side, which resulted in the concurrent opening of the airlock doors. This condition was corrected within approximately five (5) seconds. At the time of the closure of either door, secondary containment integrity was restored as the SR for one door closed was met, and no other SRs (such as negative pressure) were being exceeded. Therefore at this time, the condition no longer exists.
For the condition in which Secondary Containment did not meet the Technical Specification (TS) Surveillance Requirement (SR) 3.6.4.1.3 for at least one door in secondary containment access opening being closed, the TS Limiting Condition of Operation (LCO) 3.6.4.1 required action was to restore secondary containment to Operable status in 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. A short term LCO declaring Secondary Containment inoperable was entered at the time of discovery and subsequently exited.
An NRC notification was made via ENS 51405. This Licensing Event Report (LER) is being submitted per 10 CFR 50.73(a)(2)(v)(C) as a condition that could have prevented the fulfillment of safety function to control the release of radioactive material.
=
Background===
The Secondary Containment [EIIS identifier: NG] boundary surrounds the primary containment and refueling equipment. The boundary forms a control volume to contain, dilute, and hold up fission products. The Secondary Containment consists of four systems which include the Reactor Building, the Reactor Building Isolation and Control System, the Standby Gas Treatment System, and the Main Stack. Secondary Containment is designed to provide containment for postulated design basis accident scenarios: loss-of-coolant accident and refueling (fuel handling) accident. Since pressure may increase in Secondary Containment relative to the environmental pressure, support systems are required to maintain a differential pressure vacuum such that external atmosphere would leak into containment rather than fission products leak out.
The systems which maintain a differential pressure vacuum inside Secondary Containment include the normal Reactor Building Ventilation and Cooling (RBV) System [VA] (during normal plant operations) and the safety-related Standby Gas Treatment (SBGT) System [BH] for post-accident conditions.
Technical Specification (TS) Surveillance Requirement (SR) 3.6.4.1.3 requires one Secondary Containment access door in each access opening to remain closed. Failure to meet this SR results in the Secondary Containment Limiting Condition for Operation (LCO) not being met, and requires the Secondary Containment to be declared Inoperable.
Event Description
On September 17, 2015, with the James A. FitzPatrick Nuclear Power Plant (JAF) operating at 100 percent power, a member of the Radiation Protection (RP) department and the Nuclear Regulatory Commission (NRC) were about to conduct a walk down of the Reactor Building, and entered the north door of the north Secondary Containment access opening on Elevation 272. A chemistry contractor simultaneously entered the same Secondary Containment access opening via the opposing door on the south side, which resulted in the concurrent opening of the airlock doors. This condition was corrected within approximately five (5) seconds. At the time of the closure of either door, secondary containment integrity was restored as the SR for one door closed was met, and no other SRs (such as negative pressure) were being exceeded. Therefore at this time, the condition no longer exists.
For the condition in which Secondary Containment did not meet the Technical Specification (TS) Surveillance Requirement (SR) 3.6.4.1.3 for at least one door in secondary containment access opening being closed, the TS Limiting Condition of Operation (LCO) 3.6.4.1 required action was to restore secondary containment to Operable status in 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. A short term LCO declaring Secondary Containment inoperable was entered at the time of discovery and subsequently exited.
An NRC notification was made via ENS 51405. This Licensing Event Report (LER) is being submitted per 10 CFR 50.73(a)(2)(v)(C) as a condition that could have prevented the fulfillment of safety function to control the release of radioactive material.U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY 0MB: NO. 3150-0104 EXPIRES: 0113112017 02-2014) the NRC may not conduct or sponsor and a person is not required o resowa a he inforat on colectior
- 1. FACILJTY NAME
- 2. DOCKET
- 6. LER NUMBER
- 3. PAGE YEAR SEQUENTIAL REV James A. FitzPatrick Nuclear Power Plant 05000333 3 of 4 2015
004
00
Event Analysis
Timeline of Events on 9/17/2015 1120 Condition discovered and subsequently corrected within approximately five (5) seconds 1133 Condition Report (CR-JAF-2015-04146) initiated.
1220 Short Term LCO Entry/Exit (Late Entry)
Secondary Containment momentarily inoperable 1624 NRC notified via ENS 51405
Cause
Secondary Containment access openings are equipped with green indicating lights that are lit when the opposing access opening door is fully shut. Both parties involved indicated they observed the green indicating light prior to opening the airlock door. Therefore, the cause of this condition was determined to be simultaneous opening of the doors.
Similar Events
Internal Events No similar events were identified at JAF.
External events:
Quad Cities Nuclear Generating Station: LER 2015-008, Interlock Doors Opened Simultaneously Cause Loss of Secondary Containment.
Duane Arnold Energy Center: LER 201 5-003-01, Both Doors in Secondary Containment Airlock Opened Concurrently.
Corrective Actions
Completed Actions Both airlock doors on the north Reactor Building 272 elevation Secondary Containment access opening were closed within approximately five (5) seconds.
A prompt investigation was conducted, including interviews with all involved personnel.
Planned Actions Submittal of a License Amendment Request, Ref. TSTF-551, Revise Secondary Containment Surveillance Requirements, which is currently under NRC review.
Safety Consequence and Implications Actual Consequences There were no actual consequences of this event relative to nuclear, industrial, or radiological safety.
Potential Consequences The Secondary Containment differential pressure remained more negative than 0.25 inches of water vacuum while this condition existed. Therefore, there are no potential consequences of this event relative to nuclear, industrial, or radiological safety.U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY 0MB: NO. 3150-01 04 EXPIRES: 0113112017 02-2014)
, the NRC may not conduct or sponsor, and a person 5 not required to respond to. the ntorrnation Co action
- 1. FACILITY NAME
- 2. DOCKET
- 6. LER NUMBER
- 3. PAGE YEAR SEQUENTIAL I
REV James A. FitzPatrick Nuclear Power Plant 05000333 4 of 4 NUMBER NO.
2015
004
00 References Condition Report: CR-JAF-2015-04146, September 17, 2015, Concurrent Opening of Secondary Containment Access Airlocks Technical Specifications