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{{Adams
#REDIRECT [[05000387/LER-2016-001]]
| number = ML16145A123
| issue date = 05/24/2016
| title = LER 16-001-00 for Susquehanna, Unit 2, Regarding Secondary Containment Breach Due to Simultaneous Opening of Airlock Doors Due to Degraded Latch Mechanism
| author name = Franke J A
| author affiliation = Susquehanna Nuclear, LLC, Talen Energy
| addressee name =
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000387, 05000388
| license number = NPF-014, NPF-022
| contact person =
| case reference number = PLA-7470
| document report number = LER 16-001-00
| document type = Letter, Licensee Event Report (LER)
| page count = 5
}}
 
=Text=
{{#Wiki_filter:MAY 2 4 2016 Jon A. Franke Susquehanna Nuclear, LLC Site Vice President 769 Salem Boulevard Berwick , PA 18603 Tel. 570.542.2904 Fax 570.542.1504 Jon.Franke@TalenEnergy
.com U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 SUSQUEHANNA STEAM ELECTRIC STATION LICENSEE EVENT REPORT 50-388(387)/2016-001-00 UNIT 2 LICENSE NO. NPF-22 UNIT 1 LICENSE NO. NPF-14 PLA-7470 ENERGY 10 CFR 50.73 Docket No. 50-388 50-387 Attached is Licensee Event Report (LER) 50-388(387)/2016-001-00.
This LER repmis a condition that could have prevented fulfillment of the Secondary Containment integrity safety function.
In this event, both doors for one of the secondary containment access airlock were briefly opened simultaneously due to a degraded door latch mechanism.
This LER is being submitted pursuant to the requirements of 10 CFR 50.73(a)(2)(v)(C).
There were no actual consequences to the health and safety of the public as a result of this event. This letter contains no new regulatory commitments.
J. A. Franke
 
==Attachment:==
 
LER 50-388(387)/2016-001
-00 Copy: NRC Region I Mr. J. E. Greives, NRC Sr. Resident Inspector Ms. T. E. Hood , NRC Project Manager Mr. M. Shields, PA DEP/BRP NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 10/31/2018 (11-2015)
Estimated burden per r esponse to comply with this mandatory collection request: 80 hours.
Reported l essons learned are incorporated into the licensing proc ess and fed back to industry. (iz; LICENSEE EVENT REPORT (LER) Send comments regarding burden estimate to the FOIA, Privacy and Information Collections .......... Branch (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-000 1, or by (See Page 2 for required number of internet e-mail to lnfocollects.Resource@nrc.gov, and to the Desk Ollicer, Office of Information and digits/characters for each block) Regulatory Affairs, NEOB-10202, (3150-0104), Oflice of Management and Budget, Washington, DC 20503. II a means u sed to im pose a n i n fo r matio n collection does n ot display a cu rr e ntly val id OMB contro l number, the NRC may n ot conduc t or sponsor, and a person i s not required to r espond to, the information collection.
: 1. FACILITY NAME 2. DOCKET NUMBER r* PAGE Susquehanna Steam Electric Station Unit 2 05000388 1 of4 4. TITLE Secondary Containment Breach due to Simultaneous Opening of Airlock Doors Due to Degraded Latch Mechanism
: 5. EVENT DATE 6. LER NUMBER 7. REPORT DATE 8. OTHER FACILITIES INVOLVED Y EAR I SEQUENTIAL I REV FACILITY NAME DOCKE T NUMBER MONTH DAY Y EAR NO. MONTH DAY YEAR Susquehanna Steam Electric Station Unit 1 05000387 NUMBER FACILIT Y NAME D OCK ET NUMBER 03 29 2016 2016 -001 -00 05 2016 05000 9. OPERATING MODE 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §:(Check all that apply) D 20.2201(b)
D 20.2203(a)(3)(i)
D 50.73(a)(2)(ii)(A)
D 50.73(a)(2)(viii)(A) 1 0 20.2201(d) D 20.2203(a)(3)(ii) 0 50.73(a)(2)(ii)(B)
D 50.73(a)(2)(viii)(B) 0 20.2203(a)(1)
D 20.2203(a)(4) 0 50.73(a)(2)(iii) 0 50.73(a)(2)(ix)(A) 0 20.2203(a)(2)(i)
D 50.36(c)(1
)(i)(A) 0 50.73(a)(2)(iv)(A) 0 50.73(a)(2)(x)
D 20.2203(a)(2)(ii) 0 50.36(c)(1
)(ii)(A) 0 50.73(a)(2)(v)(A) 0 73.71(a)(4)
: 10. POWER LEVEL D 20.22 03(a)(2)(iii) 0 50.36(c)(2) 0 50.73(a)(2)(v)(B) 0 73.71(a)(5) D 20.2203(a)(2)(iv) 0 50.46(a)(3)(ii) 50.73(a)(2)(v)(C) 0 73.77(a)(1) 100 D 20.2203(a)(2)(v) 0 50.73(a)(2)(i)(A)
D 50.73(a)(2)(v)(D)
D 73.77(a)(2)(i) 0 20.2203(a)(2)(vi)
D 50.73(a)(2)(i)(B)
D 50.73(a)(2)(vii)
D 73.77(a)(2)(ii)
D 50.73(a)(2)(i)(C) 0 OTHER Specify in Abstract be l ow or in NRC Form 366A 12. LICENSEE CONTACT FOR THIS LER LICENSEE CON T ACT NUMER (Include Area Code) M. Krick, Senior EnQineer-Nuclear ReQulatory Affairs (570) 542-1818 13. COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRJBED IN THIS REPORT CAUSE SYST EM COM PONENT MANU-REPORTABLE CAUSE SYSTEM MANU-REPORTABLE FACTURER TO EPI X FACTURER TOEPIX X NG DR N/A N N/A N/A N/A N/A N/A 14. SUPPLEMENTAL REPORT EXPECTED 15. EXPECTED MONTH DAY YEAR D YES (If yes, complete 15. EXPECTED SUBMISSION DATE) SUBMISSION DATE ABSTRACT (Umit to 1400 spaces, i.e., approximate ly 15 si n gle-spaced typewritten lin es) On March 29, 2016 at approximately 23:00, two employees leaving the Unit 2 Turbine Building entered the Turbine Building to Reactor Building airlock. Prior to opening the airlock door, employees verified a green light was present, indicating the opposite airlock door was closed. The first employee entered the airlock while the other employee held the Turbine building door. As the second employee entered into the airlock, the airlock alarm was heard. As this time, a rush of air was observed from the Reactor Building side of the airlock, forcing the door open (Door 120A). Both individuals quickly closed the doors. The individuals then proceeded through the Reactor Building door to the nearest phone and informed the Control Room of the event. Having both airlock doors momentarily open simultaneously, results in a potential loss of safety function and requires reporting under 10 CFR 50.73(a)(2)(v)(C).
The cause of this event was determined to be normal wear of the Door 120A (Reactor Building airlock door) door latch. Corrective actions to address this issue include repair of the door latch mechanism.
NRC FORM 366 (11-2015)
PaQe 2 of 4 NRC FORM 366A 11-2015) U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 10/31/2018
: 1. FACILITY NAME LICENSEE EVENT REPORT (LER) CONTINUATION SHEET Susquehanna Steam Electric Station, Unit 2 NARRATIVE CONDITIONS PRIOR TO EVENT Unit 2-Mode 1, 100 percent Rated Thermal Power Unit 1 -Mode 5 , 0 percent Rated Thermal Power EVENT DESCRIPTION Estimated burden pe r response to comply with this mandatory collection request: 80 hours. Reported l essons l earned a r e incorporated into the licensing process and l ed back to industry.
Send comments regarding burden estimate to the FOIA, Privacy and Information Collections Branch (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by internet e-mail to lnfocollects.Resource@nrc.gov, and to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-10202, (3 1 50-0104), Office of Management and Budget, Washington, DC 20503. If a means used to impose an in f ormation collection does not display a currently va lid OMB control numb e r, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
: 2. DOCKET NUMBER 05000388 YEAR I 2016 3. LER NUMBER SEQUENTIAL I NUMB ER -001 REV NO. -00 On March 29, 2016 at approximately 23:00, two employees leaving the Unit 2 Turbine Building [EllS System Identifier:
NM] entered the Turbine Building to Reactor Building airlock [EllS Component Identifier:
AL] on elevation 676'. Prior to opening the airlock door [EllS Component Identified:
DR], employees verified a green light was present, indicating the opposite airlock door was closed. The first employee entered the airlock while the other employee held the Turbine building door. As the second employee entered into the airlock, the airlock alarm was heard. At this time, a rush of air was observed from the Reactor Building [EllS System Identifier:
NG] side of the airlock, forcing the door open (Door 120A). Both individuals quickly closed the doors, followed by a peer check to verify each door was properly shut. The individuals then proceeded through the Reactor Building door to the nearest phone and informed the Control Room [EllS System Identifier:
NA] of the event. CAUSE OF EVENT The direct cause of this event is normal wear of the airlock door latch. Based on investigation performed, the Door 120A latch was determined to be sticking inside the crash bar. This prevented the Reactor Building airlock door from properly latching and staying latched when differential pressure was applied to the door upon entering the airlock from the Unit 2 Turbine Building side. NRC FORM 366 (11-2015)
Paqe 3 of 4 NRC FORM 366A 11-20 1 5) U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3 150-0 1 04 EXPIRES: 10/31/2018
: 1. FACILITY NAME LICENSEE EVENT REPORT (LER) CONTINUATION SHEET Susquehanna Steam Electric Station, Unit 2 NARRATIVE ANALYSIS/SAFETY SIGNIFICANCE Es t imated b ur de n per r es p o n se t o comply wi th t hi s ma nd a t ory col l ec t io n r eques t: 80 h ou r s. R e p orte d l essons l ea rn ed a r e in cor p ora t ed int o t he li censi n g p r ocess a nd f ed back t o in dus t ry. Sen d comments r ega rd ing b u rde n es t imate t o the FO IA , Privacy a n d In fo rm ation Collectio ns B r anc h (T-5 F 53), U.S. N u clear R egula t ory Commissio n , Was hi ng t on, DC 20555-00 0 1, or b y i nt e rn e t e-m ai l to lnl oco ll ec t s.R esou r ce@n r c.gov, and t o th e Desk Off i cer, Office o f I n fo r matio n and Reg ul atory A ffairs, NEO B-1 0202 , (3 1 50-0104), O ffi ce o f Ma n age m e nt a nd Bu dge t , Was h i n g t on, D C 20503. If a m eans used to im pose a n i n fo rm ation co l lec ti o n d oes n o t display a cur r en tl y va li d OM B con t ro l nu m be r, t h e NRC may no t co n d u c t o r s p o n so r , and a p e r son i s not r equ ir ed t o r espond to, t he inf orma t io n co ll ec ti o n. 2. DOCKET NUMBER 3. LER NUMBER 05000388 Y E AR I SEQUE N T I A L I R EV NU MB ER N O. 2016 -001 -00 Technical Specification 3.6.4.1 Surveillance Requirement 3.6.4.1.3 requires that one secondary containment access door in each access opening is closed. This event is being reported pursuant to 10 CFR 50.73(a)(2)(v)(C) as having both Secondary Containment airlock doors momentarily open simultaneously results in a condition that could have prevented fulfillment of a safety function to mitigate the consequences of an accident by controlling the release of radioactive material.
There was no actual safety consequence as a r esult of this event. Engineering analysis of this event has determined that secondary containment could have performed its safety function of isolating, as assumed in the accident analysis , and also of re-establishing 0.25 in w.g. vacuum (drawdown) within the assumed accident analysis time ( 10 minutes).
Therefore, the subject event did not cause a loss of safety function.
This event will not be counted as a safety system functional failure (SSFF) for the NRC performance indicator based on the Engineering analysis supporting the system's ability to fulfill the safety function.
CORRECTIVE ACTIONS As discussed above, the cause of this event was attributed to normal wear of the airlock door latch. A work order was written to investigate and repair the Door-120A latch as necessary.
Maintenance lubricated and tightened screws on the latch mechanism; the door was then successfully tested and confirmed operable by Operations.
No regulatory commitments are associated with this report. COMPONENT FAILURE INFORMATION Reactor Building Elevation 676' Door-120A-Normal Wear. NRC FORM 366 (11-2 015)
Page 4 of 4 NRC FORM 366A 1 1-20 1 5) U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 1 0/31/2018
: 1. FACILITYNAME LICENSEE EVENT REPORT (LER) CONTINUATION SHEET Susquehanna Steam Electric Station, Unit 2 NARRATIVE PREVIOUS SIMILAR EVENTS Est i mated bu r den p er r espo n se to co m p l y w ith thi s mandatory collec ti o n req u es t: 80 ho ur s. Re p orted l esso n s lea rn ed a r e i ncorpo r a t ed i nto t h e l icensi n g process and fed back to i nd u s t ry. Se n d co m ments rega r di n g b u r de n esti m a t e to the FOIA, Privacy and Inf orma t ion Co ll ections B ra n ch (T-5 F53), U.S. N uclea r R egu l a t o ry Co mmi ss i o n, W as hin g t o n, DC 20 5 55-000 1 , or by int e rn e t e-m ai l t o l n f oco ll ects.R eso ur ce@n rc.gov, an d to t he Desk O ff ice r , O ffi ce o f In for m at i on a n d R egu l ato ry A ff a ir s, NEO B-10202, (3 1 50-0 1 04), O ff ice o f Ma n agemen t a nd Budge t , Washi n gto n , D C 20503. If a m eans use d to impose an informa ti o n co ll ec ti on d oes n ot d isplay a cur r e n tly valid OMB co n t r o l n umbe r , th e NRC may n ot conduct o r sponso r , an d a person is not r equi r e d to r espond to, the i nf or m atio n co ll ec ti o n. 2. DOCKET NUMBER 3. LER NUMBER YEAR I S E QU ENTI AL I R EV NUMBER N O. 05000388 2016 -001 -00 The following recent LERs involving loss of Secondary Containment due to door issues: LER 50-387(388)/
2016-001-00 (PLA7453), " Secondary Containment Declared Inoperable Due to an Airlock Door Open Due to Random Occurrence," dated April 18 , 2016. LER 50-387(388)/2016-002-00 (PLA7 454 ), " Secondary Containment Declared Inoperable due to an Airlock Doors Open Due to Random Occurrence," dated April 18, 2016. LER 50-387/ 2015-011-00 (PLA7 432), " Secondary Containment Declared Inoperable Due to an Airlock Door that had not been Properly Latched," dated January 29, 2016. LER 50-387(388) 2015-006-00 (PLA7383), " Secondary Containment Declared Inoperable Due to Secondary Containment Boundary Door 1 04-R Breached," dated September 18, 2015. LER 50-387/ 2015-004-00 (PLA7353), " Secondary Containment Inoperable due Secondary Containment Boundary Door Found Ajar ," dated June 25 , 2015. LER 50-387(388)/
2015-002-00 (PLA7329), " Secondary Containment lnoperability due Failure to Meet Technical Specification Surveillance Requirement 3.6.4.1.1 ," dated June 10 , 2015. LER 50-387(388)/2014-002-00 (PLA7155), " Secondary Containment Door found Ajar," dated April 9, 2014. LER 50-388(387)/
2014-001-00 (PLA7270), " Both Doors of a Secondary Containment Pe r sonnel Airlock Momentarily Open Due to a Personnel Error Resulting in Entry into Secondary Containment Technical Specification Limiting Condition for Operat i on ," dated December 31 , 2014. NR C F O RM 36 6 (11-2 015)
MAY 2 4 2016 Jon A. Franke Susquehanna Nuclear, LLC Site Vice President 769 Salem Boulevard Berwick , PA 18603 Tel. 570.542.2904 Fax 570.542.1504 Jon.Franke@TalenEnergy
.com U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 SUSQUEHANNA STEAM ELECTRIC STATION LICENSEE EVENT REPORT 50-388(387)/2016-001-00 UNIT 2 LICENSE NO. NPF-22 UNIT 1 LICENSE NO. NPF-14 PLA-7470 ENERGY 10 CFR 50.73 Docket No. 50-388 50-387 Attached is Licensee Event Report (LER) 50-388(387)/2016-001-00.
This LER repmis a condition that could have prevented fulfillment of the Secondary Containment integrity safety function.
In this event, both doors for one of the secondary containment access airlock were briefly opened simultaneously due to a degraded door latch mechanism.
This LER is being submitted pursuant to the requirements of 10 CFR 50.73(a)(2)(v)(C).
There were no actual consequences to the health and safety of the public as a result of this event. This letter contains no new regulatory commitments.
J. A. Franke
 
==Attachment:==
 
LER 50-388(387)/2016-001
-00 Copy: NRC Region I Mr. J. E. Greives, NRC Sr. Resident Inspector Ms. T. E. Hood , NRC Project Manager Mr. M. Shields, PA DEP/BRP NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 10/31/2018 (11-2015)
Estimated burden per r esponse to comply with this mandatory collection request: 80 hours.
Reported l essons learned are incorporated into the licensing proc ess and fed back to industry. (iz; LICENSEE EVENT REPORT (LER) Send comments regarding burden estimate to the FOIA, Privacy and Information Collections .......... Branch (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-000 1, or by (See Page 2 for required number of internet e-mail to lnfocollects.Resource@nrc.gov, and to the Desk Ollicer, Office of Information and digits/characters for each block) Regulatory Affairs, NEOB-10202, (3150-0104), Oflice of Management and Budget, Washington, DC 20503. II a means u sed to im pose a n i n fo r matio n collection does n ot display a cu rr e ntly val id OMB contro l number, the NRC may n ot conduc t or sponsor, and a person i s not required to r espond to, the information collection.
: 1. FACILITY NAME 2. DOCKET NUMBER r* PAGE Susquehanna Steam Electric Station Unit 2 05000388 1 of4 4. TITLE Secondary Containment Breach due to Simultaneous Opening of Airlock Doors Due to Degraded Latch Mechanism
: 5. EVENT DATE 6. LER NUMBER 7. REPORT DATE 8. OTHER FACILITIES INVOLVED Y EAR I SEQUENTIAL I REV FACILITY NAME DOCKE T NUMBER MONTH DAY Y EAR NO. MONTH DAY YEAR Susquehanna Steam Electric Station Unit 1 05000387 NUMBER FACILIT Y NAME D OCK ET NUMBER 03 29 2016 2016 -001 -00 05 2016 05000 9. OPERATING MODE 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §:(Check all that apply) D 20.2201(b)
D 20.2203(a)(3)(i)
D 50.73(a)(2)(ii)(A)
D 50.73(a)(2)(viii)(A) 1 0 20.2201(d) D 20.2203(a)(3)(ii) 0 50.73(a)(2)(ii)(B)
D 50.73(a)(2)(viii)(B) 0 20.2203(a)(1)
D 20.2203(a)(4) 0 50.73(a)(2)(iii) 0 50.73(a)(2)(ix)(A) 0 20.2203(a)(2)(i)
D 50.36(c)(1
)(i)(A) 0 50.73(a)(2)(iv)(A) 0 50.73(a)(2)(x)
D 20.2203(a)(2)(ii) 0 50.36(c)(1
)(ii)(A) 0 50.73(a)(2)(v)(A) 0 73.71(a)(4)
: 10. POWER LEVEL D 20.22 03(a)(2)(iii) 0 50.36(c)(2) 0 50.73(a)(2)(v)(B) 0 73.71(a)(5) D 20.2203(a)(2)(iv) 0 50.46(a)(3)(ii) 50.73(a)(2)(v)(C) 0 73.77(a)(1) 100 D 20.2203(a)(2)(v) 0 50.73(a)(2)(i)(A)
D 50.73(a)(2)(v)(D)
D 73.77(a)(2)(i) 0 20.2203(a)(2)(vi)
D 50.73(a)(2)(i)(B)
D 50.73(a)(2)(vii)
D 73.77(a)(2)(ii)
D 50.73(a)(2)(i)(C) 0 OTHER Specify in Abstract be l ow or in NRC Form 366A 12. LICENSEE CONTACT FOR THIS LER LICENSEE CON T ACT NUMER (Include Area Code) M. Krick, Senior EnQineer-Nuclear ReQulatory Affairs (570) 542-1818 13. COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRJBED IN THIS REPORT CAUSE SYST EM COM PONENT MANU-REPORTABLE CAUSE SYSTEM MANU-REPORTABLE FACTURER TO EPI X FACTURER TOEPIX X NG DR N/A N N/A N/A N/A N/A N/A 14. SUPPLEMENTAL REPORT EXPECTED 15. EXPECTED MONTH DAY YEAR D YES (If yes, complete 15. EXPECTED SUBMISSION DATE) SUBMISSION DATE ABSTRACT (Umit to 1400 spaces, i.e., approximate ly 15 si n gle-spaced typewritten lin es) On March 29, 2016 at approximately 23:00, two employees leaving the Unit 2 Turbine Building entered the Turbine Building to Reactor Building airlock. Prior to opening the airlock door, employees verified a green light was present, indicating the opposite airlock door was closed. The first employee entered the airlock while the other employee held the Turbine building door. As the second employee entered into the airlock, the airlock alarm was heard. As this time, a rush of air was observed from the Reactor Building side of the airlock, forcing the door open (Door 120A). Both individuals quickly closed the doors. The individuals then proceeded through the Reactor Building door to the nearest phone and informed the Control Room of the event. Having both airlock doors momentarily open simultaneously, results in a potential loss of safety function and requires reporting under 10 CFR 50.73(a)(2)(v)(C).
The cause of this event was determined to be normal wear of the Door 120A (Reactor Building airlock door) door latch. Corrective actions to address this issue include repair of the door latch mechanism.
NRC FORM 366 (11-2015)
PaQe 2 of 4 NRC FORM 366A 11-2015) U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 10/31/2018
: 1. FACILITY NAME LICENSEE EVENT REPORT (LER) CONTINUATION SHEET Susquehanna Steam Electric Station, Unit 2 NARRATIVE CONDITIONS PRIOR TO EVENT Unit 2-Mode 1, 100 percent Rated Thermal Power Unit 1 -Mode 5 , 0 percent Rated Thermal Power EVENT DESCRIPTION Estimated burden pe r response to comply with this mandatory collection request: 80 hours. Reported l essons l earned a r e incorporated into the licensing process and l ed back to industry.
Send comments regarding burden estimate to the FOIA, Privacy and Information Collections Branch (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by internet e-mail to lnfocollects.Resource@nrc.gov, and to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-10202, (3 1 50-0104), Office of Management and Budget, Washington, DC 20503. If a means used to impose an in f ormation collection does not display a currently va lid OMB control numb e r, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
: 2. DOCKET NUMBER 05000388 YEAR I 2016 3. LER NUMBER SEQUENTIAL I NUMB ER -001 REV NO. -00 On March 29, 2016 at approximately 23:00, two employees leaving the Unit 2 Turbine Building [EllS System Identifier:
NM] entered the Turbine Building to Reactor Building airlock [EllS Component Identifier:
AL] on elevation 676'. Prior to opening the airlock door [EllS Component Identified:
DR], employees verified a green light was present, indicating the opposite airlock door was closed. The first employee entered the airlock while the other employee held the Turbine building door. As the second employee entered into the airlock, the airlock alarm was heard. At this time, a rush of air was observed from the Reactor Building [EllS System Identifier:
NG] side of the airlock, forcing the door open (Door 120A). Both individuals quickly closed the doors, followed by a peer check to verify each door was properly shut. The individuals then proceeded through the Reactor Building door to the nearest phone and informed the Control Room [EllS System Identifier:
NA] of the event. CAUSE OF EVENT The direct cause of this event is normal wear of the airlock door latch. Based on investigation performed, the Door 120A latch was determined to be sticking inside the crash bar. This prevented the Reactor Building airlock door from properly latching and staying latched when differential pressure was applied to the door upon entering the airlock from the Unit 2 Turbine Building side. NRC FORM 366 (11-2015)
Paqe 3 of 4 NRC FORM 366A 11-20 1 5) U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3 150-0 1 04 EXPIRES: 10/31/2018
: 1. FACILITY NAME LICENSEE EVENT REPORT (LER) CONTINUATION SHEET Susquehanna Steam Electric Station, Unit 2 NARRATIVE ANALYSIS/SAFETY SIGNIFICANCE Es t imated b ur de n per r es p o n se t o comply wi th t hi s ma nd a t ory col l ec t io n r eques t: 80 h ou r s. R e p orte d l essons l ea rn ed a r e in cor p ora t ed int o t he li censi n g p r ocess a nd f ed back t o in dus t ry. Sen d comments r ega rd ing b u rde n es t imate t o the FO IA , Privacy a n d In fo rm ation Collectio ns B r anc h (T-5 F 53), U.S. N u clear R egula t ory Commissio n , Was hi ng t on, DC 20555-00 0 1, or b y i nt e rn e t e-m ai l to lnl oco ll ec t s.R esou r ce@n r c.gov, and t o th e Desk Off i cer, Office o f I n fo r matio n and Reg ul atory A ffairs, NEO B-1 0202 , (3 1 50-0104), O ffi ce o f Ma n age m e nt a nd Bu dge t , Was h i n g t on, D C 20503. If a m eans used to im pose a n i n fo rm ation co l lec ti o n d oes n o t display a cur r en tl y va li d OM B con t ro l nu m be r, t h e NRC may no t co n d u c t o r s p o n so r , and a p e r son i s not r equ ir ed t o r espond to, t he inf orma t io n co ll ec ti o n. 2. DOCKET NUMBER 3. LER NUMBER 05000388 Y E AR I SEQUE N T I A L I R EV NU MB ER N O. 2016 -001 -00 Technical Specification 3.6.4.1 Surveillance Requirement 3.6.4.1.3 requires that one secondary containment access door in each access opening is closed. This event is being reported pursuant to 10 CFR 50.73(a)(2)(v)(C) as having both Secondary Containment airlock doors momentarily open simultaneously results in a condition that could have prevented fulfillment of a safety function to mitigate the consequences of an accident by controlling the release of radioactive material.
There was no actual safety consequence as a r esult of this event. Engineering analysis of this event has determined that secondary containment could have performed its safety function of isolating, as assumed in the accident analysis , and also of re-establishing 0.25 in w.g. vacuum (drawdown) within the assumed accident analysis time ( 10 minutes).
Therefore, the subject event did not cause a loss of safety function.
This event will not be counted as a safety system functional failure (SSFF) for the NRC performance indicator based on the Engineering analysis supporting the system's ability to fulfill the safety function.
CORRECTIVE ACTIONS As discussed above, the cause of this event was attributed to normal wear of the airlock door latch. A work order was written to investigate and repair the Door-120A latch as necessary.
Maintenance lubricated and tightened screws on the latch mechanism; the door was then successfully tested and confirmed operable by Operations.
No regulatory commitments are associated with this report. COMPONENT FAILURE INFORMATION Reactor Building Elevation 676' Door-120A-Normal Wear. NRC FORM 366 (11-2 015)
Page 4 of 4 NRC FORM 366A 1 1-20 1 5) U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 1 0/31/2018
: 1. FACILITYNAME LICENSEE EVENT REPORT (LER) CONTINUATION SHEET Susquehanna Steam Electric Station, Unit 2 NARRATIVE PREVIOUS SIMILAR EVENTS Est i mated bu r den p er r espo n se to co m p l y w ith thi s mandatory collec ti o n req u es t: 80 ho ur s. Re p orted l esso n s lea rn ed a r e i ncorpo r a t ed i nto t h e l icensi n g process and fed back to i nd u s t ry. Se n d co m ments rega r di n g b u r de n esti m a t e to the FOIA, Privacy and Inf orma t ion Co ll ections B ra n ch (T-5 F53), U.S. N uclea r R egu l a t o ry Co mmi ss i o n, W as hin g t o n, DC 20 5 55-000 1 , or by int e rn e t e-m ai l t o l n f oco ll ects.R eso ur ce@n rc.gov, an d to t he Desk O ff ice r , O ffi ce o f In for m at i on a n d R egu l ato ry A ff a ir s, NEO B-10202, (3 1 50-0 1 04), O ff ice o f Ma n agemen t a nd Budge t , Washi n gto n , D C 20503. If a m eans use d to impose an informa ti o n co ll ec ti on d oes n ot d isplay a cur r e n tly valid OMB co n t r o l n umbe r , th e NRC may n ot conduct o r sponso r , an d a person is not r equi r e d to r espond to, the i nf or m atio n co ll ec ti o n. 2. DOCKET NUMBER 3. LER NUMBER YEAR I S E QU ENTI AL I R EV NUMBER N O. 05000388 2016 -001 -00 The following recent LERs involving loss of Secondary Containment due to door issues: LER 50-387(388)/
2016-001-00 (PLA7453), " Secondary Containment Declared Inoperable Due to an Airlock Door Open Due to Random Occurrence," dated April 18 , 2016. LER 50-387(388)/2016-002-00 (PLA7 454 ), " Secondary Containment Declared Inoperable due to an Airlock Doors Open Due to Random Occurrence," dated April 18, 2016. LER 50-387/ 2015-011-00 (PLA7 432), " Secondary Containment Declared Inoperable Due to an Airlock Door that had not been Properly Latched," dated January 29, 2016. LER 50-387(388) 2015-006-00 (PLA7383), " Secondary Containment Declared Inoperable Due to Secondary Containment Boundary Door 1 04-R Breached," dated September 18, 2015. LER 50-387/ 2015-004-00 (PLA7353), " Secondary Containment Inoperable due Secondary Containment Boundary Door Found Ajar ," dated June 25 , 2015. LER 50-387(388)/
2015-002-00 (PLA7329), " Secondary Containment lnoperability due Failure to Meet Technical Specification Surveillance Requirement 3.6.4.1.1 ," dated June 10 , 2015. LER 50-387(388)/2014-002-00 (PLA7155), " Secondary Containment Door found Ajar," dated April 9, 2014. LER 50-388(387)/
2014-001-00 (PLA7270), " Both Doors of a Secondary Containment Pe r sonnel Airlock Momentarily Open Due to a Personnel Error Resulting in Entry into Secondary Containment Technical Specification Limiting Condition for Operat i on ," dated December 31 , 2014. NR C F O RM 36 6 (11-2 015)}}

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