05000387/LER-1917-006, Regarding Control Room Envelope In-leakage Exceeded the Technical Specification Limit: Difference between revisions

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{{Adams
#REDIRECT [[05000387/LER-1917-006, Regarding Secondary Containment Declared Inoperable Due to Trip of Zone II Exhaust Fan]]
| number = ML17338A443
| issue date = 12/04/2017
| title = Regarding Control Room Envelope In-leakage Exceeded the Technical Specification Limit
| author name = Berryman B
| 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-7659
| document report number = LER 17-006-00
| document type = Letter, Licensee Event Report (LER)
| page count = 4
}}
{{LER
| Title = Regarding Control Room Envelope In-leakage Exceeded the Technical Specification Limit
| Plant =
| Reporting criterion = 10 CFR 50.73(a)(2)(v), 10 CFR 50.73(a)(2)(ii)(A), 10 CFR 50.73(a)(2)(viii)(A), 10 CFR 50.73(a)(2)(ii)(B), 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), 10 CFR 50.73(a)(2)(x), 10 CFR 50.73(a)(2)(v)(A), 10 CFR 50.73(a)(2)(v)(B), 10 CFR 50.73(a)(2)(i)(A), 10 CFR 50.73(a)(2)(i)(B), 10 CFR 50.73(a)(2)(vii), 10 CFR 50.73(a)(2)(i)
| Power level =
| Mode =
| Docket = 05000387
| LER year = 1917
| LER number = 6
| LER revision = 0
| Event date =
| Report date =
| ENS =
| abstract =
}}
 
=text=
{{#Wiki_filter:Brad Berryman Site Vice President U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Susquehanna Nuclear, LLC 769 Salem Boulevard Berwick, PA 18603 Tel. 570.542.2904 Fax 570.542.1504 Brad.Berryman@TalenEnergy.com SUSQUEHANNA STEAM ELECTRIC STATION LICENSEE EVENT REPORT 50-387(388)/2017-006-00 UNIT 1 LICENSE NO. NPF-14 UNIT 2 LICENSE NO. NPF -22 PLA-7659 TALEN~
ENERGY 10 CFR 50.73 Docket No. 50-387 50-388 Attached is Licensee Event Report (LER) 50-387(388)/2017-006-00. The LER reports an event involving control room envelope in-leakage exceeding the Technical Specification limit. This event was determined to be reportable in accordance with 10 CFR 50.73(a)(2)(v)(D) as a condition that could have prevented fulfilment of a safety function.
Should you have any questions regarding this submittal, please contact Mr. Jason Jennings, Manager-Nuclear Regulatory Affairs at (570) 542-3155.
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.
Attachment: LER 50-387(388)/2017-006-00 Copy:
NRC Region I Ms. T. E. Hood, NRC Project Manager Ms. L. H. Micewski, NRC Sr. Resident Inspector Mr. M. Shields, PA DEP/BRP
 
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 03/31/2020 (04-2017) htt!;!://www.nrc.gov/reading-rm/doc-collections/nuregs/staff/sr1 022/r3D the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
: 13. PAGE Susquehanna Steam Electric Station Unit 1 05000387 1 OF3
: 4. TITLE Control Room Envelope In-leakage Exceeded the Technical Specification Limit
: 5. EVENT DATE
: 6. LER NUMBER
: 7. REPORT DATE
: 8. OTHER FACILITIES INVOLVED SEQUENTIAL FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR REV MONTH DAY YEAR Susquehanna Steam Electric Station Unit 2 NUMBER NO.
05000388 10 06 2017 2017
:- 006
:- 00 2017 FACILITY NAME DOCKET NUMBER 05000
: 9. OPERATING MODE
: 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: Check all that apply) 1 D 20.2201(b)
D 20.2203(a)(3)(i) 0 50.73(a)(2)(ii)(A)
D 50.73(a)(2)(viii)(A)
D 20.2201 (d)
D 20.2203(a)(3)(ii) 0 50.73(a)(2)(ii)(B)
D 50.73(a)(2)(viii)(B)
D 20.2203(a)(1)
D 20.2203(a)(4)
D 50.73(a)(2)(iii)
D 50.73(a)(2)(ix)(A)
D 20.2203(a)(2)(i) 0 50.36(c)(1 )(i)(A)
D 50.73(a)(2)(iv)(A)
D 50.73(a)(2)(x)
: 10. POWER LEVEL D 20.2203(a)(2)(ii) 0 50.36(c)(1)(ii)(A)
D 50.73(a)(2)(v)(A)
D 73.71 (a)(4)
D 20.2203(a)(2)(iii)
D 50.36(c)(2)
D 50.73(a)(2)(v)(B)
D 73.71 (a)(S) 100 D 20.2203(a)(2)(iv)
D 50.46(a)(3)(ii)
D 50.73(a)(2)(v)(C)
D 73.77(a)(1)
D 20.2203(a)(2)(v) 0 50.73(a)(2)(i)(A)
~ 50.73(a)(2)(v)(D)
D 73.77(a)(2)(i)
D 20.2203(a)(2)(vi) 0 50.73(a)(2)(i)(B)
D 50.73(a)(2)(vii)
D 73.77(a)(2)(ii) 0 50.73(a)(2)(i)(C) 0 OTHER Specify in Abstract below or in NRC Form 366A
: 12. LICENSEE CONTACT FOR THIS LER LICENSEE CONTACT lrLEPHONE NUMBER (Include Area Code)
I C. E. Manges, Jr., Senior Engineer-Nuclear Regulatory Affairs 1(570) 542-3089
: 13. COMPLETE ONE UNE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT
 
==CAUSE==
SYSTEM COMPONENT MANU-REPORTABLE
 
==CAUSE==
SYSTEM COMPONENT MANU-REPORTABLE FACTURER TO EPIX FACTURER TOEPIX
: 14. SUPPLEMENTAL REPORT EXPECTED
: 15. EXPECTED MONTH DAY YEAR [8J YES (If yes, complete 15. EXPECTED SUBMISSION DATE}
D NO SUBMISSION 01 27 2018 DATE ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines)
On October 6, 2017 at 1945 hours, a loss of Control Room Habitability Envelope (CRE) was declared due to failing to meet Surveillance Requirement (SR) 3.7.3.4 during surveillance testing. The CRE is required to be maintained such that occupants can control the reactor safely under normal conditions and maintain it in a safe condition following a radiological event, hazardous chemical release, or a smoke challenge. Mitigating actions were identified and include the ability to issue potassium iodide (KI) to the control room staff and Emergency Plan responders. With implementation of the mitigating actions, the dose consequence to the control room operators and affected Emergency Plan personnel is substantially less than the regulatory limit of 5 Rem Total Effective Dose Equivalent (TEDE) for event duration.
On October 6, 2017, at 2146 hours, this condition was reported (ENS #53003) in accordance with 10 CFR 50.72(b)(3)(v)(D) as an event or condition that, at the time of discovery, could have prevented the fulfillment of the safety function needed to mitigate the consequences of an accident. There is no redundant Susquehanna Control Room Habitability Envelope.
The cause is still under investigation. Corrective actions will be determined following completion of the cause analysis.
There were no actual consequences to the health and safety of the public as a result of this event.
NRC FORM 366 (04-2017)
 
==CONDITIONS PRIOR TO EVENT==
, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
: 2. DOCKET NUMBER YEAR 05000387 2017
: 3. LER NUMBER SEQUENTIAL NUMBER
:- 006 REV NO.
:- 00 Unit 1 - Mode 1, approximately 100 percent Rated Thermal Power Unit 2 - Mode 1, approximately 100 percent Rated Thermal Power
 
==EVENT DESCRIPTION==
On October 6, 2017 at 1945 hours, a loss of Control Room Habitability Envelope (CRE) [EllS System Identifier: NA] was declared due to failing to meet Surveillance Requirement (SR) 3.7.3.4 during surveillance testing. Specifically, during testing of the "A" Control Room Emergency Outside Air Supply (CREOAS) train, the unfiltered inleakage was determined to be 222 cubic feet per minute (cfm) plus a test uncertainty of 458 cfm for a total of 680 cfm. This value exceeded the allowable in leakage value of 500 cfm. The CRE is required to be maintained such that occupants can control the reactor safely under normal conditions and maintain it in a safe condition following a radiological event, hazardous chemical release, or a smoke challenge. Technical Specification (TS) 3.7.3, Required Action 8.1, required immediate initiation of action to implement mitigating actions. The mitigating actions included the ability to issue potassium iodide (KI) to the control room staff and Emergency Plan responders. An adequate supply was verified to be available. Required Action 8.2 required that, within 24 hours, the mitigating actions be verified to ensure CRE occupant exposures to radiological, chemical, and smoke hazards will not exceed limits. Toxic chemical analysis and smoke infiltration analysis assume normal ventilation operation and are not invalidated by the failed SR 3.7.3.4 results for the CRE. Analyses of dose impact determined that, with issuance of Kl in accordance with procedures and an unfiltered inleakage of 800 cfm, the dose consequence to the control room operators and affected Emergency Plan personnel is substantially less than the regulatory limit of 5 Rem Total Effective Dose Equivalent (TEDE) for event duration.
On October 6, 2017, at 2146 hours, this condition was reported (ENS #53003) in accordance with 10 CFR 50. 72(b )(3)(v)(D) as an event or condition that, at the time of discovery, could have prevented the fulfillment of the safety function needed to mitigate the consequences of an accident. There is no redundant Susquehanna Control Room Habitability Envelope.
 
==CAUSE OF EVENT==
The cause is still under investigation. Further information associated with the cause will be provided in a supplement to this LER.
 
==ANALYSIS/SAFETY SIGNIFICANCE==
Safety significance information will be provided in the supplement to this LER.
NRC FORM 3668 (04-2017)
Page 2 of 3 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 3/31/2020 (04-2017)
LICENSEE EVENT REPORT (LER)
CONTINUATION SHEET (See NUREG-1 022, R.3 for instruction and guidance for completing this form http://www. nrc. gov/readinq-rm/d oc-collections/n u reqs/staff/sr1 022/r3D
, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
: 3. LER NUMBER YEAR Susquehanna Steam Electric Station Unit 1 05000387 2017
 
==CORRECTIVE ACTIONS==
SEQUENTIAL NUMBER
:- 006 REV NO.
:- 00 Corrective actions will be determined following completion of the cause analysis and will be provided in a supplement to this LER.
 
==COMPONENT FAILURE INFORMATION==
Component failure information will be provided in the supplement, if applicable.
 
==PREVIOUS SIMILAR EVENTS==
Previous similar events will be provided in the supplement to this LER.
NRC FORM 3668 (04-2017)
}}
 
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