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Category:Drawing
MONTHYEARML1007402622010-02-24024 February 2010
Aquifer, Samples
ML1007402142009-05-20020 May 2009
Ogcgs Radiological Survey
ML1007402042009-05-15015 May 2009
Ocgs Radiological Survey
ML1007105262009-05-0101 May 2009
Ogcgs Radiological Survey
ML0911403582009-03-20020 March 2009
Drawing - Oyster Creek Drywell Reactor Shell Sketch
ML0911403502009-03-20020 March 2009
Drawing - Figure 6 - Reactor Cavity Trough Drain
ML0911403562009-03-20020 March 2009
Drawing - Oyster Creek Drywell Reactor Cavity Section Detail a
ML0911403572009-03-20020 March 2009
Drawing - Oyster Creek Drywell Reactor Cavity Cutout
ML0911403592009-03-20020 March 2009
Drawing - Oyster Creek Drywell to Reactor Cavity Seal Detail, Detail B
ML0911403602009-03-20020 March 2009
Drawing - Oyster Creek Lower Drywell/ Sandbed Region, Detail C
ML0911403612009-03-20020 March 2009
Drawing - Oyster Creek Sectional View of Sand Bed Area at Vent Pipe
ML0911403622009-03-20020 March 2009
Drawing - Oyster Creek Reactor Building, Drywell Support Structure
ML0911403632009-03-20020 March 2009
Drawing - Oyster Creek Lower Drywell - Sandbed, Trench & Sump
ML0911807142009-03-20020 March 2009
Drawing - Bay 17 - Trench
ML0911807152009-03-20020 March 2009
Drawing - View from Inside Drywell
ML0911807162009-03-20020 March 2009
Drawing - Key Plan
ML0911807312009-03-20020 March 2009
Key Plan with Handwritten Notes
ML0911807332009-03-20020 March 2009
Figure 6 - Reactor Cavity Trough Drain, Oyster Creek Drywell General Description
ML0911403642009-03-20020 March 2009
Drawing - Bay 5 - Trench
ML1007401552009-03-0606 March 2009
Ogcgs Radiological Survey
ML0911905782008-11-0707 November 2008
E-mail from J. Richmond of USNRC to S. Pindale, J. Richmond and J. Heinly, Regarding Oc Reactor Cavity Leakage
ML0911900902008-10-21021 October 2008
E-mail from J. Richmond of USNRC to J. Kulp and S. Pindale of USNRC, Regarding Drawing Attached for Oc Outage Inspection Plan
ML0630602722006-08-0101 August 2006
E-MAIL: (PD) Drawing Requested by Labs
ML0619304012006-07-0707 July 2006
2006/07/07-Oyster Creek - Supplemental Information Related to the Aging Management Program for the Plant Drywell Shell, Associated with Amergen'S License Renewal Application
ML0522104072005-07-22022 July 2005
2005/07/22-Drawing, LR-GU-3E-243-21-1000, Rev 0, License Renewal Drawing Drywell and Torus Vacuum Relief System Flow Diagram. Sheet 1 of 1
ML0522104132005-07-22022 July 2005
2005/07/22-Drawing, LR-GU-3E-551-21-1000, Rev 0, License Renewal Drawing Nuclear Liquid Sampling System Final Fdw Facil & Thrm Cont Unit Flow Diagram. Sheet 1 of 1
ML0522104152005-07-22022 July 2005
2005/07/22-Drawing, LR-GU-3E-551-21-1001, Rev 0, License Renewal Drawing Nuclear Liquid Sampling Sys Reac Wtr Smplg STA & Cont Unit Flow Diagram. Sheet 1 of 7
ML0522104432005-07-22022 July 2005
2005/07/22-Drawing, LR-GU-3E-666-21-1000, Rev 0, License Renewal Drawing Hydrogen and Oxygen Monitoring System Drywell Flow Diagram. Sheet 1 of 1
ML0522104482005-07-22022 July 2005
2005/07/22-Drawing, LR-GU-3E-822-21-1000, Rev 0, License Renewal Drawing Standby Gas Treatment Flow Diagram. Sheet 1 of 1
ML0522104522005-07-22022 July 2005
2005/07/22-Drawing, LR-GU-3E-861-21-1000, Rev 0, License Renewal Drawing Emergency Diesel Generator Air Cooling System Flow Diagram. Sheet 1 of 1
ML0522104582005-07-22022 July 2005
2005/07/22-Drawing, LR-GU-3E-861-21-1001, Rev 0, License Renewal Drawing Emergency Diesel Generator Water Cooling System Flow Diagram. Sheet 1 of 1
ML0522104652005-07-22022 July 2005
2005/07/22-Drawing, LR-GU-3E-861-21-1002, Rev 0, License Renewal Drawing Emergency Diesel Generator Lube Oil System Flow Diagram. Sheet 1 of 1
ML0522104702005-07-22022 July 2005
2005/07/22-Drawing, LR-GU-3E-862-21-1000, Rev 0, License Renewal Drawing Emergency Diesel Generator Diesel Fuel Oil Stor & Trans Sys Flow Diagram. Sheet 1 of 1
ML0522205992005-07-22022 July 2005
2005/07/22-Drawing, LR-GU-3E-871-21-1000, Rev 0, License Renewal Drawing Domestic Water & Pretreatment System Flow Diagram. Sheet 2 of 3
ML0522205962005-07-22022 July 2005
2005/07/22-Drawing, LR-GU-3E-871-21-1000, Rev 0, License Renewal Scoping Drawing Domestic Water and Pretreatment System Flow Diagram. Sheet 1 of 3
ML0726804281997-09-30030 September 1997
Department of the Army, Corps of Engineers, Permit Number CENAP-OP-R-199701765-39
ML0726405991982-05-14014 May 1982
Jersey Central Power & Light Co. Boundary Map of Former Finninger Farm
2010-02-24
[Table view]
Category:E-Mail
MONTHYEARML22235A7862022-08-23023 August 2022
Acceptance Review: Exemption Request from 10 CFR 20, Appendix G, LLW Shipping Investigation Requirements
ML21181A1882021-06-30030 June 2021
E-mail from S. Johnston, Holtec, to A. Snyder and F. Bower, NRC - Oyster Creek Nuclear Generating Station - Readiness Status for ISFSI Only Inspection
ML21175A2092021-06-24024 June 2021
E-mail from A. Sterdis to P. Longmire - Oyster Creek Nuclear Generating Station: ISFSI-only Physical Security Plan (Stating Implementation Intent)
ML21162A3602021-06-11011 June 2021
E-mail Response from the State of New Jersey Regarding the Pending Revision to the Emergency Plan to Reflect Independent Spent Fuel Storage Installation Only Status
ML21162A1172021-06-11011 June 2021
E-mail to HDI: Acceptance Review - FOF Exemption
ML21168A0172021-06-10010 June 2021
E-mail from HDI: RAI Response
ML21161A2572021-06-0707 June 2021
State Consultation: ISFSI-only Physical Security Plan (Email Response)
ML21175A0712021-06-0202 June 2021
Issuance of Request for Additional Information: Oyster Creek Nuclear Generating Station. Request for Amendment to Technical Specifications
ML21148A0562021-05-27027 May 2021
E-mail to State of New Jersey Informing of the Pending Revision to the Emergency Plan to Reflect Independent Spent Fuel Storage Installation Only Status
ML21132A3182021-05-12012 May 2021
E-Mail from V. Gubbi, DEP to Z. Cruz, NRC - Oyster Creek Nuclear Generating Station - State of New Jersey Response to the Pending Revision to the Defueled Technical Specifications to Reflect Independent Spent Fuel Storage Installation Only
ML21132A0312021-05-11011 May 2021
E-mail to State of New Jersey Informing of the Pending Revision to the Physical Security Plan to Reflect Independent Spent Fuel Storage Installation Only Status
ML21119A1422021-04-28028 April 2021
E-mail to State of New Jersey Informing of the Pending Revision to the Emergency Plan to Reflect Independent Spent Fuel Storage Installation Only Status
ML21113A0742021-04-23023 April 2021
Acceptance Review Email - April 20, 2021 Oyster Creek Request for Exemption from 10 CFR Part 73 Requirements Due to Covid
ML21099A0382021-04-0808 April 2021
Email from Z. Cruz to A. Sterdis - Request for Additional Information - HDI Request for Approval of Oyster Creek Nuclear Generating Station Independent Spent Fuel Storage Installation Facility Only Emergency Plan
ML21085A4872021-03-26026 March 2021
E-mail from Z. Cruz to A. Sterdis - Acceptance Review: Oyster Creek Nuclear Generating Station - Request for Approval of Independent Spent Fuel Storage Installation Only Permanently Defueled Technical Specifications
ML21064A2432021-03-0505 March 2021
Email from Z. Cruz to A. Sterdis Acceptance Review_ Oyster Creek Nuclear Generating Station - Request for Approval of Independent Spent Fuel Storage Installation Facility Only Emergency Plan and Emergency Action Level Scheme
ML21064A2392021-03-0202 March 2021
E-mail from Z. Cruz to A. Sterdis Acceptance Review - Oyster Creek Nuclear Generating Station - Request for Approval of Independent Spent Fuel Storage Installation Only Physical Security Plan
ML20345A1462020-12-0909 December 2020
E-mail - Response to Request for Additional Information: HDI Request for One-Time Exemption from Part 73, Appendix B FOF Requirements
ML20335A3112020-11-30030 November 2020
Request for Additional Information Regarding Request for a one-time Exemption from Part 73, Appendix B Requirements for Oyster Creek Nuclear Generating Station
ML20332A1472020-11-24024 November 2020
Acceptance Review: November 20 2020 Exemption Request from 10 CFR Part 73 Appendix B Requirements for Oyster Creek
ML20297A2372020-10-22022 October 2020
Request for Additional Information - HDI Fleet Decommissioning Quality Assurance Program
ML20279A5082020-10-0505 October 2020
Email to Holtec - Response to Notification of Oyster Creek Onsite Property Insurance Coverage
ML20266G4032020-09-22022 September 2020
Acceptance Review Email - Request for Approval of HDI Fleet Decommissioning Quality Assurance Program, Revision 0
ML20134H8742020-05-12012 May 2020
Request for Additional Information Regarding Request for Temporary Exemption from Part 73, Appendix B Requirements
ML20133J9182020-05-11011 May 2020
Acceptance Review Email - Oyster Creek Request for Exemption from Part 73 Qualification Requirements
ML20120A0252020-04-22022 April 2020
NRR E-mail Capture - (External_Sender) Oyster Creek Sea Turtle Handling and Conservation Recommendation Obligations
NRC-2019-0073, Response from NEIMA Local Community Advisory Board Questionnaire 10-30-2019 R Discenza2019-10-30030 October 2019
Response from NEIMA Local Community Advisory Board Questionnaire 10-30-2019 R Discenza
ML19344C8022019-10-20020 October 2019
Response from NEIMA Local Community Advisory Board Questionnaire 10-20-2019 a Dressler
ML19344C8002019-10-0909 October 2019
Response from NEIMA Local Community Advisory Board Questionnaire 10-09-2019 W Mcmullin
ML19344C7982019-10-0909 October 2019
Response from NEIMA Local Community Advisory Board Questionnaire 10-09-2019 M Noto
ML19344C7992019-10-0909 October 2019
Response from NEIMA Local Community Advisory Board Questionnaire 10-09-2019 s Feldman
ML19344C7932019-10-0909 October 2019
Response from NEIMA Local Community Advisory Board Questionnaire 10-09-2019 C Bischoff
ML19344C7962019-10-0909 October 2019
Response from NEIMA Local Community Advisory Board Questionnaire 10-09-2019 G Adams
ML19344C7912019-10-0808 October 2019
Response from NEIMA Local Community Advisory Board Questionnaire 10-08-2019 J Branciforte
ML19344C7902019-10-0808 October 2019
Response from NEIMA Local Community Advisory Board Questionnaire 10-08-2019 Anonymous
ML19344C7892019-10-0505 October 2019
Response from NEIMA Local Community Advisory Board Questionnaire 10-05-2019 P Dressler
ML19263D1222019-09-20020 September 2019
for Your Action Request for Additional Information Hdi Oyster Creek PSDAR
ML19214A0452019-08-0202 August 2019
NRC to NMFS, Revised Proposed Action for Oyster Creek Endangered Species Act Section 7 Consultation
ML19182A3422019-07-0101 July 2019
Transaction
ML19178A0702019-06-26026 June 2019
Email to State of New Jersey - Oyster Creek - Request Comments on Proposed Amendment to Remove Reference to the Oyster Creek Cyber Security Plan and Update License Condition 2.C.(4) in the Renewed Facility License
ML19196A3422019-06-20020 June 2019
Email: Courtesy Notice on the Issuance of the Oyster Creek License Transfer and Exemption (Sierra Club)
ML19196A3342019-06-20020 June 2019
Email: Courtesy Notice on the Issuance of the Oyster Creek License Transfer and Exemption
ML19162A2242019-06-11011 June 2019
NRC to NMFS, NRC Responses to NMFS Requests for Additional Information for Oyster Creek ESA Section 7 Consultation
NRC-2018-0237, Comment from Paul Dressler of the Concerned Citizens for Lacey Coalition, Regarding the Oyster Creek Nuclear Plant License Transfer Application2019-06-0707 June 2019
Comment from Paul Dressler of the Concerned Citizens for Lacey Coalition, Regarding the Oyster Creek Nuclear Plant License Transfer Application
ML19155A1182019-06-0404 June 2019
Incoming E-mail from State of New Jersey on the Oyster Creek Exemption for Reduced Insurances and Use of Decommissioning Trust Fund for Spent Fuel Management and Site Restoration
ML19155A1192019-06-0404 June 2019
State of New Jersey Comments - Oyster Creek Conforming Amendment Associated with the Oyster Creek Generating Station License Transfer Application
ML19154A0582019-05-31031 May 2019
E-mail Response from State of New Jersey Dated May 31, 2019, Notification-and-Request-Oyster Creek License Transfer Application L-2018-LLM-0002
ML19158A2912019-05-30030 May 2019
NRR E-mail Capture - Oyster Creek ESA Consultation: Information Requests from NMFS
ML19158A2772019-05-28028 May 2019
NRR E-mail Capture - Oyster Creek ESA Consultation: Information Requests from NMFS
ML19148A4392019-05-24024 May 2019
NMFS to NRC, Requests for Additional Information to Support Oyster Creek Reinitiated Section 7 Consultation
2022-08-23
[Table view] |
Text
John Richmond From: John Richmond -
Sent: Tuesday, October 21, 2008 1:30 PM To: Jeffrey Kulp; Stephen Pindale Cc: Ronald Bellamy; Scott Barber; Marc Ferdas; Michael Modes; Timothy OHara; Richard Conte
Subject:
Drawing attached for RE: OC Outage Inspection Plan Attachments: OC View from inside Drywell.jpg; OC Drywell Elevation & Regions.bmp; OC Drywell Key Plan.jpg; OC Drywell Liner Thicknesses.jpg; OC Drywell Support Structure.jpg; OC Drywell Trench, Bay-5.jpg; OC Drywell Trench, Bay-1 7.jpg; OC Drywell X-section.jpg; OC Rx Cavity Detail.jpg; OC Rx Cavity Trough Drain Detail.jpg; OC Sandbed Detail-i .jpg; OC Sandbed Detail-2.jpg; OC Sandbed, Trench, & Sump.jpg All of the attached drawings came from Public Records (ACRS & ASLB presentations).
These drawings may be helpful when discussing various drywell issues.
From: John Richmond Sent: Monday, September 29, 2008 2:04 PM To: Marc Ferdas; Jeffrey Kulp Cc: Stephen Pindale; Ronald Bellamy; Scott Barber
Subject:
OC Outage Inspection Plan Marc/Jeff, can you include the following License Renewal items in the Resident Outage Inspection Plan?
- 1. As soon as reasonably achievable after the Drywell is opened, verify condition of both D/W Trenches (dry, wet, water stains, etc.). Pictures are optional, but always nice.
- 2. Within about 1-shift after the cavity is flooded up, verify the reactor cavity trough drain leakage rate (we do expect some leakage). After the initial check, continue to check it, about once per day, for a day or two, to see if the leakage rate changes. During 1R21 (2006), the continuous leakage was identified at about 1 gpm, while the cavity was flooded.
- 3. Within about 1-shift after the cavity is flooded up, verify the 5 D/W sandbed drains, drain collection bottles.
No water or leakage is expected.
- 4. AmerGen is to apply a strippable coating, as a sealant, in the reactor cavity prior to flood up, to limit cavity seal leakage that could end up in the sandbed area. While you are welcome to observe or inspect this item, my team will verify this item, by a records review, after we arrive on-site.
- 5. During this outage, AmerGen is suppose to replace some ESW pipe. I understand the pipe has already been laid/installed, and is waiting to be "tied-in" during the outage. Did the Residents observe any portion of the new EtSW pipe installation?
Thanks John Richmond
Received: from R1CLSTRO1 .nrc.gov ([148.184.99.7]) by R1 MS01 .nrc.gov
([148.184.99.10]) with mapi; Tue, 21 Oct 2008 13:29:47 -0400 Content-Type: application/ms-tnef; name="winmail.dat" Content-Transfer-Encoding: binary From: John Richmond <John. Richmond@nrc.gov>
To: Jeffrey Kulp <Jeffrey.Kulp@nrc.gov>, Stephen Pindale
<Stephen. Pindale@nrc.gov>
CC: Ronald Bellamy <Ronald.Bellamy@nrc.gov>, Scott Barber
<Scott.Barber@nrc.gov>, Marc Ferdas <Marc.Ferdas@nrc.gov>, Michael Modes
<Michael.Modes@nrc.gov>, Timothy OHara <Timothy.OHara@nrc.gov>, Richard Conte
<Richard. Conte@nrc.gov>
Date: Tue, 21 Oct 2008 13:29:44 -0400
Subject:
Drawing attached for RE: OC Outage Inspection Plan Thread-Topic: Drawing attached for RE: OC Outage Inspection Plan Thread-Index: AckiXbveQcOAazRyQ8uNcVdUr4+eVgRRFfBQ Message-ID: <2856BC46F6A308418F033D973BBOEE72AA2A4DC877@R1CLSTRO1 .nrc.gov>
References:
<2856BC46F6A308418F033D973BBOEE72969755C4FC@R1CLSTRO1 .nrc.gov>
In-Reply-To: <2856BC46F6A308418F033D973BBOEE72969755C4FC@R1CLSTRO1 .nrc.gov>
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<2856BC46F6A308418F033D973BBOEE72AA2A4DC877@R1 CLSTR01.nrc.gov>
MIME-Version: 1.0
VIEW FROM INSIDE DRYWELL UPPER CURB - EL. 12'.3" TOP OF SANDBED
. _jL Al A1.
0 El E 8i ,7 4 LOWER CURB A6 A A A 4
<1 A DRYWELL FLOOR - EL., 10'-3"
REACTOR BUILDING, DRYWELL SUPPORT STRUCTURE
-I--
I CONTAINMENT SHELL SANDBED REGION---\ EL. 23'-6" GRADE EL. 23'-6" J
&REACTOR VESSEL CURB DRYWELL FLOOR
~/
EL. 10'-3"
-EL. 5'-D" LIMIT OF TORUS - MEMBRANE L
1" . L-EL. 4'-6""
WATERPROOFING N'
,1 MEMBRANE WATERPROOFING (TYP ALL AROUND)
. .- PEDESTAL - WATER STOP (TYP)
TYGON ALL AROUND)
TUBING
¸---.--'i -'
,.- I P Uh MAI 4>
- EL. _l9-j A-A 5 GALLON io,-o- *POLY BOTTLE 1 4r44
-CONCRETE MAT I *.* I '~4Z A:'
-. A .' A *~' -A ~
L 43'-6" EMEMBRANE WATERPROOFING LEVELING SLAB
REACTOR CAVITY STAINLESS STEEL LINER----
CONCRETE
REACTOR VESSEL DRYWELL AND REACTOR CAVITY SECTION DETAIL "A"
Head Iso Elevation 94'-9" View Cy 00 Azimut
.900 AzimL Elevation 71'-10" 2700 Azin Elevation 65'-4" "L.- Knuc 50'-11 ' Uppe
--- Mid(
tion 37'43 Per!
ition 27'-6" & Equ
.tion 23'-6" H Lower CVer (10
\
4
.4 TOP OF SANDBED EL. 12'-3" & UPPER CURB LOWER CURB EL. 11-DRYVA WALL
FLOOR EL. 10'-3" 44 4 4, 4.
4 . 4 4
-. .4
- ~* 4
-. A REG ION .4 4.
4
- 4 4 4'.
.4 ' 4"
"*,o EL. 8'-99 EXCAVATION 4 4
4'
.4 4.
4/ "
,t,
.4 A
BAY 5 -TRENCH
.4 4 4.
4 44
.4
.4' 4 4 44 A ~.
4..4
.4. 4 4'
4.
.4_ 44 ~ .
4.
.4 :4 4
4 4
4 4.. .4, 4
. 4 4. 4 4 4
A 4 .
- , 4 4a
DRYWELL TO REACTOR CAVITY SEAL DETAIL DETAIL 'B' OBSERVEDDAMAGE-AT LIP OF TROUGH CORRECTED IN 1988
EL, 87'-6" (12)
F EL. 51f-.1O (8.9)/
TRENH .. EL. 60'-1 (100)
NOTE:
NUMBERS IN PARENTHESES, REFER TO.THE ATTACHEDGRAPH IDENTIFCATION NUMBERS KEY PLAN
TOD OF SANDBED EL. 12"--3" & UPPER CURB LOWER CURB EL. 11'-0" DRYWELL WALL FLOOR EL. 10'-Y" 4 4 .4
- 4-
>4 4 4, '
h,' 4. 4 4.. 4 A
.4 4
SANDBED
'4 REGION EL. 9'-3 .4
.4 3/4 4> 4 4 - .4 4 '.4' A 4 44 4.
'0.
- 4. .4 47 A' ~ 4 .
4, .4 4 '4 4 4 4 4- 4. 4 44
.4' 44 A
4' 4.4. ~
4' 4 44' A ,,
"'.4
- 4. 4 4 4 4,. 4
.,A A ~ 4.
'4 . 4
,4'4 , .4
.4' 4 '. 44, 4 4 '. .4 4 4.
LOWER DRYWELL/SANDBED REGION NOTE:
LEAKAGE PATH FROM OUTER DRYWELL TO OUTER DETAIL C SANDBED SHELL /
SANDBED REGION 15">
.BOTTOM F SANDBED
° -l E ,
DRYWE.LL
/_ N EL. 87'-5"
'7,. UT READINGS IN THIS AREA EL. 51'-10" ___EL. 60'- 10"
,, UT READINGS IN THIS AREA EL. 50'-2" UT READINGS IN THESE AREAS EL. _12'-,3" EL. 8'- 11 TOP OF SANDBED BOTTOM OF SANDBED SUPPORT SKIRT -
(SEE DETAIL 1) 1.154" UT READINGS IN THIS AREA-
DETAIL WA" DETAIL "B' DETAIL 'C'
i 6
SURE PLATE SAND BED AREA 0.770" THK EL. 12'-3"-
TOP OF SANDBED & UPPER CURB RADIUS = 19'-5 7/16" 1.154" THK PLATE EL. 8'-1 1" STABILIZING RING - EL. 8'--1 "
EL. 6.'-10 5/16'----
4' DRAIN PIPE (5 PLACES) 0.676" THK PLATE
( DRYWELL BOTTOM I
-EL. 2'-3" 1/2" PLATE
-- -EL. (-)0'-1" SECTIONAL VIEW OF SAND BED AREA AT VENT PIPE
LOWER DRYWELL-SANDBED, TRENCH & SUMP ELEVATION LOOKING WEST