Letter Sequence Request |
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CAC:MF9307, Addition of New Tech Spec on RCS Boron Limits and Revisions to Tech Spec 3.3.1 to Address Rwfs (Approved, Closed) |
Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance, Acceptance
- Supplement, Supplement, Supplement, Supplement, Supplement, Supplement
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MONTHYEARML17053B3932017-01-17017 January 2017 License Amendment Request for the Transition to Westinghouse Core Design and Safety Analyses Project stage: Request ML17054C2262017-01-17017 January 2017 License Amendment Request for the Transition to Westinghouse Core Design and Safety Analyses - WCAP-18083-NP, Rev 0, Westinghouse Revised Thermal Design Procedure Uncertainty Calculations Project stage: Request ML17054C2292017-01-17017 January 2017 License Amendment Request for the Transition to Westinghouse Core Design and Safety Analyses - Responses to NRC RAIs on August 2013 Methodology Transition LAR Submittal Project stage: Response to RAI ML17054C2272017-01-17017 January 2017 License Amendment Request for the Transition to Westinghouse Core Design and Safety Analyses - Alternative Source Term, Rev 1 Project stage: Request ML17151A9972017-03-0909 March 2017 Wolf Creek Revision 30 to Updated Final Safety Analysis Report, Chapter 3.0, Design of Structures, Components, Equipment, and Systems Project stage: Request WO 17-0026, Errata for License Amendment Request for Transition to Westinghouse Core Design and Safety Analyses2017-03-22022 March 2017 Errata for License Amendment Request for Transition to Westinghouse Core Design and Safety Analyses Project stage: Request ML17088A3312017-03-22022 March 2017 Transmittal of the Kansas Water Pollution Control Permit and Authorization to Discharge Under the National Pollutant Discharge Elimination System Project stage: Request ML17100A2662017-04-18018 April 2017 Supplemental Information Needed for Acceptance of Requested Licensing Action Transition to Westinghouse Core Design and Safety Analyses Project stage: Acceptance Review ET 17-0011, Response to Supplemental Information Needed for Acceptance of Requested Licensing Action Transition to Westinghouse Core Design and Safety Analyses2017-05-0404 May 2017 Response to Supplemental Information Needed for Acceptance of Requested Licensing Action Transition to Westinghouse Core Design and Safety Analyses Project stage: Request ML17132A3632017-05-15015 May 2017 Acceptance of Requested Licensing Action License Amendment Request for the Transition to Westinghouse Core Design and Safety Analyses in Addition to Adopting of Alternative Source Term Project stage: Acceptance Review ML17136A3592017-05-22022 May 2017 Request for Withholding Information from Public Disclosure, 11/14/2016(CAW-16-4499), Affidavit Executed by James A. Gresham, Westinghouse Electric Company LLC Enclosure I of the Letter Dated 01/17/2017 Project stage: Withholding Request Acceptance ML17137A2862017-05-22022 May 2017 Request for Withholding Information from Public Disclosure, 11/14/16 (CAW-16-4500) Affidavit Executed by James A. Gresham, Westinghouse Electric Company LLC for Enclosure VI to the Letter Dated 1/17/17 Project stage: Withholding Request Acceptance ML17166A0382017-06-14014 June 2017 NRR E-mail Capture - Request for Additional Information - License Amendment Request for Transition to Westinghouse Core Design and Safety Analyses Including Adoption of Alternative Source Term Project stage: RAI ET 17-0016, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analyses2017-07-13013 July 2017 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analyses Project stage: Response to RAI ML17265A0142017-09-21021 September 2017 NRR E-mail Capture - Request for Additional Information - License Amendment Request for Transition to Westinghouse Core Design and Safety Analyses Project stage: RAI ML17291A7102017-10-17017 October 2017 NRR E-mail Capture - Request for Additional Information - License Amendment Request (LAR) for Transition to Westinghouse Core Design and Safety Analyses Including Adoption of Alternative Source Term Project stage: RAI ET 17-0024, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analyses Including Adoption of Alternative Source Term2017-10-18018 October 2017 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analyses Including Adoption of Alternative Source Term Project stage: Response to RAI ML17297B7972017-10-31031 October 2017 Request for Withholding Information from Public Disclosure (CAC No. MF9307; EPID L 2017-LLA-0211) Project stage: Withholding Request Acceptance ET 17-0025, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analyses Including Adoption of Alternative Source Term2017-11-14014 November 2017 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analyses Including Adoption of Alternative Source Term Project stage: Response to RAI ML17331A1782017-12-0404 December 2017 Request for Additional Information License Amendment Request for Transition to Westinghouse Core Design and Safety Analyses Including Adoption of Alternate Source Term (CAC No. MF9307; EPID L-2017-LLA-0211) Project stage: RAI WO 18-0004, Response to Request for Additional Information Re License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of .2018-01-15015 January 2018 Response to Request for Additional Information Re License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of . Project stage: Response to RAI ET 18-0004, Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term2018-01-29029 January 2018 Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term Project stage: Supplement ML18066A0502018-03-0808 March 2018 Regulatory Audit Plan for March 19-21, 2018, in Support of the LAR for Transition to Westinghouse Core Design and Safety Analyses Including Alternative Source Term (CAC No. MF9307;EPID L-2017-LLA-0211) Project stage: Approval L-2018-077, Schedule for Re-Analysis of Turkey Point Licensing Basis Analyses Affected by PAD5 Implementation2018-03-27027 March 2018 Schedule for Re-Analysis of Turkey Point Licensing Basis Analyses Affected by PAD5 Implementation Project stage: Request ML18114A1162018-04-19019 April 2018 SAP-18-34, Supplemental 30 Day Responses to NRC Request for Additional Information Regarding Wolf Creek Generating Station Transition to Westinghouse Safety Analysis and Alternate Source Term Methodologies Project stage: Supplement ET 18-0012, Operating Corp., Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term2018-04-19019 April 2018 Operating Corp., Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term Project stage: Supplement ML18115A3522018-05-0303 May 2018 Request for Withholding Information from Public Disclosure, Affidavit Dated April 16, 2018 Supplemental 30 Day Responses to NRC RAI WCGS Transition to Westinghouse Safety AST Methodolgies Project stage: RAI ML18107A7562018-05-0303 May 2018 Regulatory Audit Summary License Amendment Request for Transition to Westinghouse Core Design and Safety Analyses Including Adoption of Alternative Source Term (CAC MF9307; EPID L-2017-LLA-0211) Project stage: Other ET 18-0018, Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term2018-06-19019 June 2018 Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term Project stage: Supplement ML18183A5832018-07-23023 July 2018 Request for Withholding Information from Public Disclosure - 6/18/18 Affidavit Executed by Edmond J. Mercier, Westinghouse Electric Company Adoption of AST Amendment Request(Cac No. MF9307; EPID L-2017-LLA-0211) Project stage: Withholding Request Acceptance WO 18-0034, Operating Corp., Additional Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term2018-08-0909 August 2018 Operating Corp., Additional Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term Project stage: Supplement ML18270A0942018-10-0404 October 2018 Request for Additional Information License Amendment Request for Transition to Westinghouse Methodology for Selected Accident and Transient Analyses Project stage: RAI 05000482/LER-2018-001, Inappropriate Use of Blind Flange for Containment Isolation Valve Results in Condition Prohibited by Technical Specifications2018-10-0404 October 2018 Inappropriate Use of Blind Flange for Containment Isolation Valve Results in Condition Prohibited by Technical Specifications Project stage: Request ML18332A1772018-10-25025 October 2018 Email Slides for 10/30 Public Meeting Project stage: Request ML18313A2252018-10-25025 October 2018 Westinghouse Affidavit CAW-18-4828 - Application for Withholding Proprietary Information from Public Disclosure Project stage: Request ML18299A0492018-10-30030 October 2018 Accident Analyses Methodology Transition LAR Public Meeting Project stage: Meeting ML18304A1052018-11-0505 November 2018 Request for Additional Information License Amendment Request for Transition to Westinghouse Core Design and Safety Analyses and Alternative Source Term (CAC No. MF9307; EPID L-2017-LLA-0211) Project stage: RAI WO 18-0047, Timeline for Response to RAI for License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term2018-11-15015 November 2018 Timeline for Response to RAI for License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term Project stage: Response to RAI WO 18-0044, Clean Revised Technical Specification Pages for License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term2018-11-15015 November 2018 Clean Revised Technical Specification Pages for License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term Project stage: Request ML18313A2542018-11-16016 November 2018 Summary of Public Meeting with Wolf Creek Nuclear Operating Corporation Regarding License Amendment Request for Transition to Westinghouse Core Design and Safety Analyses for Wolf Creek Generating Station Project stage: Meeting ML18327A1342018-11-30030 November 2018 Request for Withholding Information from Public Disclosure, Affidavit Dated October 25, 2018, Executed by Mr. Paul A. Russ, Westinghouse (CAC No. MF9307; EPID L-2017-LLA-0211) Project stage: Withholding Request Acceptance ET 18-0035, Operating Corp., Supplemental Response to RAI for License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term2018-12-0606 December 2018 Operating Corp., Supplemental Response to RAI for License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term Project stage: Supplement ML18360A0342018-12-21021 December 2018 NRR E-mail Capture - Review Schedule for Wolf Creek Generating Station License Amend Request (LAR) for Transition to Westinghouse Core Design and Safety Analyses Including Adoption of Alternative Source Term Project stage: Approval ET 19-0008, Response to Request for Additional Information Related to Thermal Conductivity Degradation for License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption2019-03-0505 March 2019 Response to Request for Additional Information Related to Thermal Conductivity Degradation for License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption Project stage: Response to RAI ML19070A1392019-03-0505 March 2019 Response to Request for Additional Information Related to Thermal Conductivity Degradation for License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption. Project stage: Request ML19070A1162019-03-0505 March 2019 Westinghouse, Responses to NRC Request for Additional Information Documented in ADAMS Accession No. ML 18270A094 on the Core Design and Safety Analyses Methodology Transition Program Project stage: Response to RAI ML19099A1772019-04-16016 April 2019 Request for Withholding Information from Public Disclosure, 2/13/19 Affidavit Executed by Stephen Rigby, Westinghouse Electric Company LLC RAI Response Related to Adoption of Alternative Source Term (CAC MF9307; EPID L-2017-LLA-0211) Project stage: RAI ML19122A2552019-05-0202 May 2019 Closed Predecisional Enforcement Conference with an Employee of Wolf Creek Nuclear Operating Corporation Project stage: Request ML19100A1222019-05-31031 May 2019 Issuance of Amendment No. 221 License Amendment Request for Transition to Westinghouse Core Design and Safety Analyses Including Adoption of Alternative Source Term Project stage: Approval 2018-10-30
[Table View] |
text
W$LFCREEK
'NUCLEAR OPERATING CORPORATION Robert J. Bayer Plant Manager U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 October 4, 2018 WO 18-0041
Subject:
Docket No. 50-482: Licensee Event Report 2018-001-00, "Inappropriate Use of Blind Flange for Containment Isolation Valve Results in Condition Prohibited by Technical Specifications" To Whom It May Concern:
The enclosed Licensee Event Report (LER) 2018-001-00 is being submitted pursuant to 10 CFR 50.73(a)(2)(i)(B) as a condition prohibited by Technical Specifications.
This letter contains no commitments. If you have any questions concerning this matter, please contact me at (620) 364-4015, or Cynthia R. Hafenstine at (620) 364-4204.
RJB/rlt
Enclosure:
LER 2018-001-00 cc:
K. M. Kennedy (NRC), w/e B. K. Singal (NRC), w/e N. H. Taylor (NRC), w/e Senior Resident Inspector (NRC), w/e Sincerely, fft~
Robert J. Bayer P.O. Box 411 / Burlington, KS 66839 / Phone: (620) 364-8831 An Equal Opportunity Employer M/F/HCNET
NRCFORM366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY 0MB: NO. 3150-0104 EXPIRES: 03/31/2020 (04-2018)
', the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
3.Page Wolf Creek Generating Station 05000 482 1
OF 4
- 4. Title Inappropriate Use of Blind Flange for Containment Isolation Valve Results in Condition Prohibited by Technical Specifications
- 5. Event Date
- 6. LER Number
- 7. Report Date
- 8. Other Facilities Involved I
Sequential I Rev Facility Name Docket Number Month Day Year Year Number No.
Month Day Year 05000 Facility Name Docket Number 05 15 2018 2018 -
001 -
00 10 04 2018 05000
- 9. Operating Mode
- 11. This Report is Submitted Pursuant to the Requirements of 1 O 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)
D 20.2201(d)
D 20.2203(a)(3)(ii)
D 50. 73(a)(2)(ii)(B)
D 50.73(a)(2)(viii)(B) 4 D
D 20.2203(a)(1)
D 20.2203(a)(4),
D 50. 73(a)(2)(iii) 50.73(a)(2)(ix)(A)
D 20.2203(a><2>(i)
D 50.36(c)(1)(i)(A)
D 50.73(a)(2)(iv)(A)
D 50.73(a)(2)(x) 1 O. Power Level D 20.2203(a)(2)(ii)
D 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)(5)
D 20.2203(a)(2)(iv)
D 50.46(a)(3)(ii)
D 50.73(a)(2)(v)(C)
D 73.77(a)(1)
NIA D 20.2203(a)(2)(v)
D 50.73(a)(2)(i)(A)
D 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)
~D 50.73(a)(2)(i)(C)
D Other (Specify in Abstract below or in The individual testing identified that valve GTHZ0006 (containment shutdown purge supply side outside containment isolation valve) had a leak rate above that allowed by TS. The valve was declared inoperable and TS LCO 3.6.3 Condition D was entered at 0255 Central Daylight Time (CDT) on May 15, 2018. With the blind flanges installed, all of the other containment shutdown purge and minipurge supply side valves successfully passed the leakage rate testing.
Because this testing was performed close to the end of RF22, it was decided to leave the blind flanges installed in accordance with TS LCO 3.6.3, Required Action D.1 which requires that the affected flow path be isolated by use of at least one closed and de-activated automatic valve, closed manual valve, or blind flange. The plant was in Mode 5 at this point, but since LCO 3.6.3 is applicable in Modes 1, 2, 3, and 4, the completion of Required Action D.1 was necessary for the plant to enter Mode 4. The plant entered Mode 4 on May 15, 2018, at 0510 CDT.
On August 8, 2018, it was discovered that using a blind flange to meet the Required Actions for Condition D of TS LCO 3.6.3 is not allowed by Wolf Creek Nuclear Operating Corporation (WCNOC) procedure Al 26C-004, Technical Specification Application for Containment Isolation Valves. Step 6.2.2.6.c of this procedure states "Because they are non-safety related and non-seismic, the installed blind flanges cannot be used to satisfy LCO 3.6.3, Required Action D.1." So while TS LCO 3.6.3 would allow blind flanges to isolate the containment shutdown purge isolation valves, this would require the use of safety-related and seismically qualified flanges and piping. As such, on August 8, 2018, at 1545 CDT, WCGS re-entered TS LCO 3.6.3 Condition D to perform Required Action D.1. Required Action D.1 was completed at 1633 CDT on August 8 by ensuring that the inside containment shutdown purge and minipurge supply isolation valves were closed and de-energized.
REPORT ABILITY TS LCO 3.6.3 Condition D, Required Action D.1 has a Completion Time of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. However, since the containment minipurge supply inside containment valve was not de-energized upon entry into Mode 4, Condition D existed for approximately 85 days (from May 15 when WCGS entered Mode 4 until August 8). Since this is longer than the allowed Completion Time for Required Action D.1, this event is being reported in accordance with 10 CFR 50.73(a)(2)(i)(B) as an operation or condition prohibited by TS.
It may also be noted that a violation of LCO 3.0.4.a occurred in connection with the plant entering a mode of applicability of LCO 3.6.3. With an LCO not met, LCO 3.0.4.a only permits entry into a mode of applicability of that LCO when the associated Required Actions to be entered permit continued operation in the applicable mode for an unlimited period of time. With Required Action D.1 of LCO 3.6.3 not actually being met, entry into Mode 4 wouldn't have been allowed.
CAUSE
This is a legacy issue. TS Bases 3.6.3 for Required Action D.1 was never updated to reflect that the blind flange currently allowed to be installed per sysiem design, could not be used to meet the Condition and Required Actions to isolate the penetration.
CORRECTIVE ACTIONS
Training was initiated for Operations personnel in both initial and requalification training to clarify that the blind flanges can not be used to meet Required Action D.1. A revision to the TS Bases 83.6.3 has been initiated to either remove the use of the currently designed blind flange, or add information that procedure Al 26C-004 needs to be reviewed. WC NOC is planning to submit a license amendment request at some point in the future to remove the use of a blind flange to meet TS LCO 3.6.3, Required Action D.1.
SAFETY SIGNIFICANCE
The safety significance of the event was low. The containment isolation function was maintained by the containment purge and minipurge supply inside containment isolation valves remaining shut. The total containment "as-found" minimum pathway leak rate remained within the limits of TS 3.6.1 during the time when the blind flange was installed.
OPERATING EXPERIENCE/PREVIOUS EVENTS None Page 4
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| 05000482/LER-2018-001, Inappropriate Use of Blind Flange for Containment Isolation Valve Results in Condition Prohibited by Technical Specifications | Inappropriate Use of Blind Flange for Containment Isolation Valve Results in Condition Prohibited by Technical Specifications | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 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)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000482/LER-2018-002, Modification Activities Affected Control Room Envelope Boundary Causing a Condition Prohibited by Technical Specifications | Modification Activities Affected Control Room Envelope Boundary Causing a Condition Prohibited by Technical Specifications | 10 CFR 50.73(a)(1), Submit an LER 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 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)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) |
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