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MONTHYEARML19189A2032019-07-0101 July 2019 Delivery Package - Oyster Creek Indemnity Agreeement B-37 Amendment 19 ML18187A3762018-07-0606 July 2018 NRC Region I Twitter Feeds 4-1 to 6-30-2018 ML17075A0102017-03-0909 March 2017 Regulatory Conference-List of Attendees - March 9, 2017 ML16285A3212016-10-12012 October 2016 ROP PI Frequently Asked Questions (Faqs): 13-05 ML15153A3142015-05-28028 May 2015 Aam Attendance Lists ML15231A3642015-05-27027 May 2015 FOIA/PA-2014-0204 - Resp 1 - Final, Group a ML15093A2852015-03-12012 March 2015 Enclosures 3 and 4: Cover Sheet for CD-R Labeled Re Pertinent Site Data (Not Added) and Summary of Regulatory Commitments ML15071A1192015-03-0202 March 2015 Attachment 1 - Response to the Request for Additional Information - License Amendment Request to Adopt Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors RA-15-019, Attachment 1 - Response to the Request for Additional Information - License Amendment Request to Adopt Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors2015-03-0202 March 2015 Attachment 1 - Response to the Request for Additional Information - License Amendment Request to Adopt Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors ML14147A0132014-05-22022 May 2014 Annual Assessment Meeting May 22 2014 Attendance List ML15016A1512014-05-19019 May 2014 Final Qa/Related Forms (Folder 1) ML13364A2832013-12-30030 December 2013 Announcement of 2014 Generic Fundamentals Examination Administration Dates-Letter Dated Dec 30, 2013 ML13143A3312013-06-0606 June 2013 Operating Boiling-Water Reactor Licensees with Mark 1 and Mark 2 Containments Addresses List - Enclosure 2 ML13035A2642013-02-22022 February 2013 Ltr. to Sen. R. Menendez from Chairman Allison Macfarlane - Oyster Creek Generating Station - Enclosure ML13199A5032012-07-23023 July 2012 Final ASP Analysis - Oyster Creek Nuclear Generating Station (219-12-001) ML12170A4602012-06-18018 June 2012 Public Meeting Attendance Sheet, June 6, 2012 ML12056A0522012-03-12012 March 2012 Enclosure 6 - List of Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status ML1117502192011-06-22022 June 2011 NRC Inspection Findings Related to Closed Cooling Water Systems (1/1/2004 to 6/22/2011) ML1115201992011-05-26026 May 2011 Aam Attendance Lists, May 26, 2011 ML1015302922010-05-25025 May 2010 Oc Sign-in Sheets for Aam ML1019304602010-03-25025 March 2010 List of Historical Leaks and Spills at Us Commercial Nuclear Power Plants ML1007401682010-02-24024 February 2010 Attachment 9 Micro ALARA Plan Work Sheet, Rev. 9 ML1007005152010-02-24024 February 2010 Wo# R2119514 ML1007005092010-02-24024 February 2010 Attachment 7.1 Unconditional Release Survey Form ML1007105582010-02-24024 February 2010 Attachment 2 Rescue Team Pre-Plan Form.. ML1007005142010-02-24024 February 2010 Determination of Outside Tank Activity, Rev. 2 ML0932703152009-11-20020 November 2009 Table C-II.1, 2008 REMP Drinking Water Results ML0934106552009-11-0606 November 2009 Oc Debrief, Stand-Alone Report ML0932006272009-09-17017 September 2009 External Communications ML0919804622009-06-17017 June 2009 Input for 71003 Q, Regarding Oyster Creek Lic Renewal ML0919606062009-06-17017 June 2009 Commitment Inspection Per IP 71003 - App. C Mc 2515, Infrequent Procedures Lessons Learned and Key Questions Developed (as of 12/18/2008) ML0920200552009-06-17017 June 2009 License Renewal Inspection NRC Discussions with Nj DEP Engineers ML0919805042009-06-17017 June 2009 Exex Summary of Inspection Results ML0919805032009-06-17017 June 2009 Key Messages for Oyster Creek ML0919802312009-06-17017 June 2009 Commitment Inspection Per IP 71003 - App. C Mc 2515, Infrequent Procedures Status and Next Steps (as of 12/18/2008) ML0919802322009-06-17017 June 2009 Commitment Inspection Per IP 71003 - App. C Mc 2515, Infrequent Procedures Lessons Learned and Key Questions Developed (as of 12/30/2008) ML0919805002009-06-17017 June 2009 License Renewal ML0919804682009-06-17017 June 2009 Commitment Inspection Per IP 71003 - App. C Mc 2515, Infrequent Procedures Lessons Learned and Key Questions Developed (as of 12/30/2008) ML0919805022009-06-17017 June 2009 Key Messages of Oyster Creek ML1007402172009-06-11011 June 2009 AR Search Results for Tritium ML1007402152009-05-20020 May 2009 Sample from Yard Transfer House ML1007402652009-05-19019 May 2009 Attachment 3 Pre-Dive Checklist ML1007402122009-05-19019 May 2009 Attachment 3 Pre-dive Checklist ML1007402132009-05-19019 May 2009 Sample from Yard Outside Tanks ML1007402072009-05-18018 May 2009 Ogcgs Radiological Survey ML1007402082009-05-18018 May 2009 Ogcgs Radiological Survey ML1007402102009-05-18018 May 2009 Attachment 3 Pre-Dive Checklist ML1007402052009-05-15015 May 2009 Sample from Turbine Bldg General ML1007402032009-05-14014 May 2009 Sample from Yard Outside Tanks ML1007402022009-05-13013 May 2009 Sample from Yard Outside Tanks 2019-07-01
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Exec Summary of Inspection Results E ER EXEpTI" Observed actions to evaluate primary containment structural integrity" Observed selected activities described in SER Appendix-A, "Commitments for LR" Because the License has not been renewed* Observed activities will be documented (i.e., factual based observations)
- No assessment was made regarding implementation of SER described activity* e.g., no conclusions whether proposed commitments were implemented
- No assessment or evaluation of activity effectiveness or adequacy was made* No safety assessment of the observed activities described in SER App-A was made" Reviewed 2 change packages for activities described in SER App-A* A summary of the change will be documented
- No assessment of administrative controls was made* No evaluation of technical adequacy was made* An Unresolved Item (URI) will be opened to evaluate whether any existing current licensing basis commitments were not adequately performed, and to assess the safety significance for any related performance deficiency Inspection Highlights (1) SER App-A Item 27, ASME Section XI, Subsection IWE, Part (2)A strippable coating will be applied to the reactor cavity liner to prevent water intrusion into the gap between the drywell shield wall and the drywell shell during periods when the reactor cavity is flooded.* From Oct 29 to Nov 7, the strippable coating limited leakage into the cavity trough drain at < 1 gpm" On Nov 7, the observed leakage rate-in the cavity trough drain took a step change to 4 to 6 gpm" Water was subsequently identified in 4 sand bed bays* AmerGen identified several likely or contributing causes:* A portable water filtration unit was improperly placed in the reactor cavity, which resulted in flow discharged directly on the strippable coating* An oil spill into the cavity may have affected the coating integrity* No post installation inspection of the coating had been performed* AmerGen stated follow-up UTs will re-evaluate the drywell shell next outage.(2) SER App-A Item 27, ASME Section Xl, Subsection IWE, Part (3)Sand bed region drains will be monitored daily during refueling outages.* Sand bed drains were remotely monitored by checking poly bottles, attached via tygon tubing to funnels hanging below the drain lines* The drain lines were not directly observed* After the reactor cavity was drained, 2 of 5 tygon tubes were found disconnected, laying on the floor* Sand Bed Bay 11 drain line poly bottle was empty during each daily check until Nov 15 (cavity was drained on Nov 12), when it was found full (> 4 gallons).
Bay 11 was entered, visually inspected, and found dry.Ndoin In f~ts mmrd was d~etede Mi mOrhdow of th nfeorm aof nkm~AM/V 1j73 (3) SER App-A Item 27, ASME Section Xl, Subsection IWE, Part (3)Reactor cavity seal leakage trough drains and the drywell sand bed region drains will be monitored for leakage. Periodically.
- Cavity trough drain line was found isolated during a boroscope examination to verify no line blockage* On Oct 27, the drain line was isolated to install a tygon hose to allow drain flow to be monitored* On Oct 29, the reactor cavity was filled" AmerGen monitored the drain line monitored during cavity flood-up, and daily thereafter
- On Oct 31, a boroscope examination identified the drain line isolation valve had been left closed" When the drain line isolation valve was opened, about 3 gallons of water drained out, then the drain flow subsided to about an 1/8 inch stream (< 1 gpm)* Drain flow remained at < 1 gpm until Nov 7, the strippable coating started to de-laminate
- Drywell external surface in the sand bed region had a 100% visual examination is adequately protected by an epoxy coating and moisture barrier seal.* 2008 & historical UT results at 23 ft and above indicate shell thickness is close to nominal values.* Observed outage-related activities described in SER as Proposed License Conditions" Perform Full Scope inspections of sand bed region every other outage* Monitor drywell trenches for water every refueling outage (until trenches restored)* We reviewed 2 change packages for activities described in SER* Bolting Integrity Program (commitment 12)* Rx Vessel Axial Weld Examination Relief Request (commitment 48)(b)(5) 2* Strippable Coating to Prevent Water Intrusion into gap between drywell and shield wall" Daily monitoring of Sand Bed Drains* Periodic monitoring of Cavity Trough Drain L- (b)(5) ' Direct visual inspection inside all 10 sand bed bays was performed.
As a result, there was no un-identtied or un-evaluated moisture or water intrusion.
All bays were inspected and verified dry, after the cavity was drained, and before final bay close-out.