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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217D4031999-10-0606 October 1999 Summarizes Series of Four Revs That Have Been Made to SNEC Emergency Response Procedure & Emergency Plan Since 970408. Revs Include Changes to Reflect Current Site Conditions & Changes in Organizational Structure ML20216J9811999-10-0404 October 1999 Forwards Insp Rept 50-146/99-202 on 990830-0902.No Violations Noted.Insp Consisted of Selective Exams of Procedures & Representative Records,Interviews with Personnel & Observations of Activities in Progress ML20209B9971999-06-29029 June 1999 Forwards 1998 Annual Rept for Saxton Nuclear Experimental Corp (Snec).Rept Covers Period Beginning 980101-981231 ML20195E0131999-06-0303 June 1999 Provides Encl Info as Evidence of Jcp&L,Meed & Penelec Commitment to Assure Continued Financial Support of Decommissioning Efforts of SNEC ML20206G6341999-05-0303 May 1999 Requests Info on How SNEC Will Show Compliance with Requirements in 10CFR50.75 on How SNEC Will Provide Reasonable Assurance That Funds Will Be Available for Completion of Decommissioning Process for Plant ML20206F6451999-04-29029 April 1999 Forwards 1998 Annual Radioactive Release Rept for SNEC & Rev 0 to Odcm. Explanations of Attachments 1-9,listed ML20206D1211999-04-27027 April 1999 Informs of Completion of Acceptance Review of Saxton Nuclear Experimental Facility License Termination Plan Submitted on 990203.Concludes That LTP Does Not Contain Sufficient Info at Present Time to Initiate Detailed Review ML20206G0351999-04-27027 April 1999 Forwards Proprietary 10CFR20.2206(b) Personnel Exposure Rept for Saxton Nuclear Experimental Corp.Rept Contains Info Required to Identify Total Number of Individuals for Whom Personnel Monitoring Was Required.Proprietary Info Withheld ML20205H1081999-03-31031 March 1999 Forwards Current Funding Status for Decommissioning Funds Established for OCNPP,TMI-1,TMI-2 & SNEC ML20204H7851999-03-22022 March 1999 Forwards Insp Rept 50-146/99-201 on 990216-18.No Violations Noted.Nrc Questionnaire Re Yr 2000 Concerns Encl ML20198A4031998-12-10010 December 1998 Forwards Insp Rept 50-146/98-204 on 981013-1106.No Violations Noted.No Response to Ltr Required ML20154K1181998-10-13013 October 1998 Forwards Insp Rept 50-146/98-203 on 980914-17.No Violations Noted ML20153C4241998-09-21021 September 1998 Responds to Requesting NRC Review Aspects of 980624 Application from Saxton Nuclear Experimental Corp & Gpu Nuclear,Inc for Regulatory Relief from DOT Shipping Requirements.Srvts Should Be Classified as LSA-III ML20237D9951998-08-24024 August 1998 Informs That Staff Does Not Object to Blending of Guide Blocks to Lower Core Plate & Determined That Guide Blocks & Plate Permanently Connected ML20236N8891998-06-24024 June 1998 Submits Two Complete Copies of Gpu Nuclear'S Requests for Exemptions,Re Shipment of Sg,Pressurizer & Reactor Vessel. Detailed Exemption Requests & Supporting Documentation Are Provided in Enclosed Attachments ML20249A2391998-06-11011 June 1998 Corrects 980420 Safety Evaluation for Amend 15 to License DPR-04 & 980409 EA & Finding of No Significant Impact.Ea Section 3.2.2 Does Rate Should Be Changed to 200 Msv Per H ML20249A6901998-06-11011 June 1998 Forwards Insp Rept 50-146/98-202 on 980511-13.No Violations Noted ML20248D6981998-05-28028 May 1998 Forwards Annual Rept & Radiological Environ Monitoring Rept for 970101-1231 for Saxton Nuclear Experimental Corp ML20216B6441998-05-0808 May 1998 Forwards Request for Addl Info Re Saxton Nuclear Experimental Facility.Various Facility Components Will Be Shipped off-site for Disposal as Radwaste ML20217A9641998-04-20020 April 1998 Forwards Amend 15 to License DPR-4 & Safety Evaluation. Amend Allows Decommissioning of Saxton Nuclear Experimental Corp Facility ML20217H2231998-04-17017 April 1998 Forwards Personnel Exposure Rept for Saxton Nuclear Experimental Corp for Calendar Year 1997.W/o Encl ML20216D0611998-04-0909 April 1998 Forwards Environ Assessment & Finding of No Significant Impact & Being Sent to Office of Federal Register for Publication.Concludes That No Significant Environ Impact Attributable to Proposed Action ML20217P7701998-03-31031 March 1998 Provides Results of Calculations Performed to Evaluate Dose to Public to Be Expected from Hypothetical Spill of Tritiated Water Being Stored in SNEC Facility Containment Vessel.Scenarios Found to Have No Significant Public Health ML20217P4181998-03-0303 March 1998 Provides Response to Question 7 of RAI Dtd 980128.Response Will Be Incorporated as Suppl 1 to Facility Decommissioning Environ Rept ML20203A5771998-02-0909 February 1998 Forwards RAI Re Amend Request for License DPR-4 Submitted 981125.Response Requested to Be Provided within 30 Days of Date of Ltr ML20202F6961998-02-0909 February 1998 Provides Response to Questions Re Apparent Undocumented Changes to Saxton Nuclear Experimental Corp Decommissioning QA Plan ML20202B2351998-02-0303 February 1998 Responds to 980128 RAI Re TS Change Request 59.Response Includes Proposed Revised Pages to Facility License,Ts, Updated Sar,Decommissioning QA Plan & Figures to Post Shutdown Activities Rept.W/Certificate of Svc ML20199F2321998-01-27027 January 1998 Forwards Request for Addl Info Re Amend to License DPR-4. Responses Requested to Be Provided within 30 Days of Dtd Ltr ML20217J7751997-10-0909 October 1997 Submits Reply to Discussing Decommissioning Activities at Facility.Decommissioning Requested to Be Delayed for 25 Yrs to Allow for Addl Radioactive Decay ML20211C2371997-09-16016 September 1997 Forwards Rev 0 to Procedure 6575-PLN-4542.09, SNEC Facility Process Control Program, for Review & Approval.Activities Will Be Initiated Starting W/Item 1.2.2.3 of Figure 2.2-4 of Decommissioning Plan When Approval of Tscr 59 Is Obtained ML20210Q2211997-08-21021 August 1997 Forwards Response to Requests for Addl Info & 0806.Info Suppls Previous Responses to Questions,Addresses Recent Questions on ODCM & Incorporates Editorial Comments Commited by Telcon.Revised TS & Updated SAR Encl ML20217H4291997-08-0606 August 1997 Forwards RAI Re Amend Request for License DPR-4.Reply Requested within 30 Days of Dtd Ltr ML20217G9271997-08-0505 August 1997 Informs That Responsibility for Non-Power Reactor Insp Program Has Been Transfered from Regional Ofc to Nrr.All Activities Re Non-Power Reactors Including Licensing,Insp & Operator Licensing Will Be Responsibility of NRR ML20141C6541997-06-16016 June 1997 Clarifies Statements in Safety Insp Rept 50-146/97-01 for Saxton Nuclear Experimental Corp Facility,That Do Not Reflect Utils Practices or Intentions ML20141C4001997-06-16016 June 1997 Forwards Procedure 6575-ADM-4500.06, Emergency Response Procedure & Emergency Plan, That Was Inadvertently Overlooked & Not Included as Attachment in Submittal, ML20217Q5871997-06-11011 June 1997 Provides Concerns & Suggestions Re Gpu Decommissioning Plan ML20140C1271997-05-30030 May 1997 Forwards Response to 970408 RAI Re TS Change Request 59 & Revised Pages to Change Request Which Includes Rev to Original Text Based Upon Response Provided ML20140C9261997-05-30030 May 1997 Forwards Responses to 970424 RAI Re Questions Resulting from Review of SNEC Decommissioning QA Program ML20138B6261997-04-24024 April 1997 Forwards Request for Addl Info Re Amend Request for License DPR-4.Response Requested within 30 Days of Ltr Date ML20137R7911997-04-0909 April 1997 Forwards RAI Re Request for Amend to Facility License DPR-4 ML20140D3761997-04-0303 April 1997 Forwards 10CFR20.2206(b) 1996 Personnel Exposure Rept for Snec,Containing Info Required to Identify Total Number of Individuals for Whom Personnel Monitoring Was Required & Statistical Summary of Personnel Monitoring Info.W/O Encl ML20140B7131997-03-18018 March 1997 Forwards Insp Rept 50-146/97-01 on 970127-29.No Violations Noted ML20136E2041997-03-0606 March 1997 Forwards Notice of Consideration of Issuance of Amend to Facility License & Proposed NSHC Determination & Opportunity for Hearing Re 961125 Request to Amend Facility License DPR-4 ML20134K1961997-02-11011 February 1997 Expresses Appreciation for Participation in 970128 Public Meeting on Post-Shutdown Decommissioning Activities Rept for Facility.Transcript of Meeting Encl ML20149M6621997-01-22022 January 1997 Forwards Copy of Notice That Appeared in 961219 Federal Register Re Public Meeting on post-shutdown Decommissioning Activities Rept for SNEC Facility & Agenda for Meeting ML20133N4001997-01-21021 January 1997 Informs That NRC Planning to Hold Public Meeting on post- Shutdown Decommissioning Activities Rept for SNEC Facility in Sexton,Pa on 970128 ML20133P9381997-01-21021 January 1997 Forwards Insp Rept 50-146/96-01 on 961119-21.No Violations Noted ML20133E1121997-01-0808 January 1997 Informs That NRC Planning to Hold Public Meeting on post- Shutdown Decommissioning Activities Rept for SNEC Facility on 970128 ML20134P3351996-11-25025 November 1996 Forwards TS Change Request 59,submitting Decommissioning TSs ML20134L7311996-11-0808 November 1996 Submits site-specific Cost Estimate for Saxton Nuclear Experimental Corp Facility as Required by 10CFR50.82(a)(8)(ii) & Satisfies Commitment to Have an Approved Quality Assurance Plan,Per 10CFR71.101 1999-06-03
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217D4031999-10-0606 October 1999 Summarizes Series of Four Revs That Have Been Made to SNEC Emergency Response Procedure & Emergency Plan Since 970408. Revs Include Changes to Reflect Current Site Conditions & Changes in Organizational Structure ML20209B9971999-06-29029 June 1999 Forwards 1998 Annual Rept for Saxton Nuclear Experimental Corp (Snec).Rept Covers Period Beginning 980101-981231 ML20195E0131999-06-0303 June 1999 Provides Encl Info as Evidence of Jcp&L,Meed & Penelec Commitment to Assure Continued Financial Support of Decommissioning Efforts of SNEC ML20206F6451999-04-29029 April 1999 Forwards 1998 Annual Radioactive Release Rept for SNEC & Rev 0 to Odcm. Explanations of Attachments 1-9,listed ML20206G0351999-04-27027 April 1999 Forwards Proprietary 10CFR20.2206(b) Personnel Exposure Rept for Saxton Nuclear Experimental Corp.Rept Contains Info Required to Identify Total Number of Individuals for Whom Personnel Monitoring Was Required.Proprietary Info Withheld ML20205H1081999-03-31031 March 1999 Forwards Current Funding Status for Decommissioning Funds Established for OCNPP,TMI-1,TMI-2 & SNEC ML20248D6981998-05-28028 May 1998 Forwards Annual Rept & Radiological Environ Monitoring Rept for 970101-1231 for Saxton Nuclear Experimental Corp ML20217H2231998-04-17017 April 1998 Forwards Personnel Exposure Rept for Saxton Nuclear Experimental Corp for Calendar Year 1997.W/o Encl ML20217P7701998-03-31031 March 1998 Provides Results of Calculations Performed to Evaluate Dose to Public to Be Expected from Hypothetical Spill of Tritiated Water Being Stored in SNEC Facility Containment Vessel.Scenarios Found to Have No Significant Public Health ML20217P4181998-03-0303 March 1998 Provides Response to Question 7 of RAI Dtd 980128.Response Will Be Incorporated as Suppl 1 to Facility Decommissioning Environ Rept ML20202F6961998-02-0909 February 1998 Provides Response to Questions Re Apparent Undocumented Changes to Saxton Nuclear Experimental Corp Decommissioning QA Plan ML20202B2351998-02-0303 February 1998 Responds to 980128 RAI Re TS Change Request 59.Response Includes Proposed Revised Pages to Facility License,Ts, Updated Sar,Decommissioning QA Plan & Figures to Post Shutdown Activities Rept.W/Certificate of Svc ML20211C2371997-09-16016 September 1997 Forwards Rev 0 to Procedure 6575-PLN-4542.09, SNEC Facility Process Control Program, for Review & Approval.Activities Will Be Initiated Starting W/Item 1.2.2.3 of Figure 2.2-4 of Decommissioning Plan When Approval of Tscr 59 Is Obtained ML20210Q2211997-08-21021 August 1997 Forwards Response to Requests for Addl Info & 0806.Info Suppls Previous Responses to Questions,Addresses Recent Questions on ODCM & Incorporates Editorial Comments Commited by Telcon.Revised TS & Updated SAR Encl ML20141C4001997-06-16016 June 1997 Forwards Procedure 6575-ADM-4500.06, Emergency Response Procedure & Emergency Plan, That Was Inadvertently Overlooked & Not Included as Attachment in Submittal, ML20141C6541997-06-16016 June 1997 Clarifies Statements in Safety Insp Rept 50-146/97-01 for Saxton Nuclear Experimental Corp Facility,That Do Not Reflect Utils Practices or Intentions ML20217Q5871997-06-11011 June 1997 Provides Concerns & Suggestions Re Gpu Decommissioning Plan ML20140C9261997-05-30030 May 1997 Forwards Responses to 970424 RAI Re Questions Resulting from Review of SNEC Decommissioning QA Program ML20140C1271997-05-30030 May 1997 Forwards Response to 970408 RAI Re TS Change Request 59 & Revised Pages to Change Request Which Includes Rev to Original Text Based Upon Response Provided ML20140D3761997-04-0303 April 1997 Forwards 10CFR20.2206(b) 1996 Personnel Exposure Rept for Snec,Containing Info Required to Identify Total Number of Individuals for Whom Personnel Monitoring Was Required & Statistical Summary of Personnel Monitoring Info.W/O Encl ML20134P3351996-11-25025 November 1996 Forwards TS Change Request 59,submitting Decommissioning TSs ML20134L7311996-11-0808 November 1996 Submits site-specific Cost Estimate for Saxton Nuclear Experimental Corp Facility as Required by 10CFR50.82(a)(8)(ii) & Satisfies Commitment to Have an Approved Quality Assurance Plan,Per 10CFR71.101 ML20134F3221996-10-25025 October 1996 Forwards SNEC Facility USAR to Incorporate Changes Commensurate W/Snec Facility Condition as It Makes Transition from Safstor to Active Decommissioning & Dismantlement ML20129G9531996-09-30030 September 1996 Provides Clarification of Approach Util Proposes to Fulfill Requirements Specified in New 50.82 Re SNEC Facility ML20117C2011996-08-20020 August 1996 Forwards Addendum to 1995 Saxton Nuclear Experimental Corp 960524 Annual Rept ML20115K0511996-07-18018 July 1996 Forwards Responses to 960606 Request for Addl Info Re Questions Resulting from Review of SNEC Facility Decommissioning Plan & Environ Rept ML20117N6901996-06-17017 June 1996 Informs NRC That Transfer to Gpun management-related Responsibilities for SNEC Facility as Set Forth by Order Approving Transfer Issued on 960510 Completed.Signed Copy of Amend 23 to Indemnity Agreement B-5 Encl ML20112D0091996-05-24024 May 1996 Responds to Request for Addl Info Re Tech Spec Change Request 57,which Addresses Proposed Expansion of Permissible Work Scope at SNEC Facility ML20107K0711996-04-24024 April 1996 Submits Response to RAI Re TS Change Request 57 Which Addresses Proposed Expansion of Permissible Work Scope at Facility ML20101C5621996-03-13013 March 1996 Provides Addl Info in Support of 951121 LAR ML20101B8741996-03-0808 March 1996 Requests NRC Approval to Leave Shield Blocks & Steel Plates in SNEC Facility Containment Vessel,In Place After Completion of Reactor/Fuel Storage Cavity Characterization Activities ML20100P3731996-02-28028 February 1996 Submits Revs to No Significant Hazards Consideration Analysis Based on Conversation W/Snec Facility Project Manager Re Deficiencies Found in Text Supporting Proposed Changes Contained in SNEC Tscr 57 ML20149K8021996-02-16016 February 1996 Forwards Rev 0 of SNEC Facility Decommissioning Plan ML20100H6121996-02-16016 February 1996 Responds to 950818 RAI Re Inadvertent Breach of Facility Containment Vessel Liner During Core Bore Operations in Support of Characterization.Rev 0 to Program 6250-PGD-2720 & Rev 0 to Procedure 6575-ADM-4500.07 Encl ML20100F4571996-02-0202 February 1996 Forwards Application for Amend to License DPR-4,proposing Expansion of Permitted Principal Activities within Exclusion Area,Certificate of Service & Safety Evaluation & Determination of No Significant Hazards Considerations ML20097G3341995-12-21021 December 1995 Requests Consideration of Amend Application Re Transfer of All mgt-related Responsibilities to SNEC ML20087H8211995-08-11011 August 1995 Forwards Agreement Which Describes & Governs Relationship Between SNEC & Gpun,In Response to NRC RAI Re TS Change Request 56 ML20087F0941995-08-0808 August 1995 Informs of Recent Action by Licensee Board of Directors to Name Fd Hafer as SNEC President as Replacement for Je Hildebrand & Ga Kuehn to Position of SNEC Vice President & General Manager Replacing Ba Good ML20087J7541995-07-27027 July 1995 Forwards Responses to RAI Re 15 Day Rept on Inadvertent Breach of Snef Containment Vessel Liner & Status Activities Associated W/Installation of Permanent Plug or Seal.Root Cause/Human Performance Evaluation Results Encl ML20086B8421995-06-28028 June 1995 Forwards Saxton Nuclear Experimental Corp 1994 Annual Rept for Saxton Nuclear Experimental Facility for 940101-941231 ML20086A5481995-06-23023 June 1995 Forwards Addendum to TS Change Request 56 to License DPR-4, Revising TS Pages 1,2 & 8 to Change Organization Performing Remainder of Characterization Activities & Future Decommissioning Activities to Assure Linkage W/Licensee ML20092B3441995-06-0707 June 1995 FOIA Request for Correspondence Between Westinghouse & AEC Re Westinghouse Work on Saxton Experimental Reactor in Saxton,Pa Between Years of 1956 & 1974 ML20084J2641995-06-0202 June 1995 Forwards Request for Amend to DPR-4 TSs (TS Change Request 56) ML20082K2891995-04-0606 April 1995 Provides Addl Info Re 950327 Meeting Between Gpu & NRC Concerning Idea of Independent Inspector.News Article from Altoona Mirror Which Author Believe Accurately Represents Bedford County Commissioners Viewpoint Encl ML20076M3371994-10-28028 October 1994 Responds to RAI Re TS Change Request 55 ML20072C2181994-08-0808 August 1994 Forwards Application for Tscr to Revise Content & Format of Existing TS & Analysis Applying Standards of 10CFR50.92 in Making Significant Hazards Considerations Determination ML20062L7301993-12-20020 December 1993 Forwards Responses to NRC Questions Resulting from Review of TS Change Request 54.Revised TS Pages Also Encl ML20057A6371993-09-0808 September 1993 Forwards 10CFR20.407 Personnel Exposure Rept for 1992.Late Submittal Is Result of Administrative Error,Identified by Internal QA Audit.Corrective Action Taken ML20056G8191993-08-31031 August 1993 Forwards Penelec/Gpu Internal Affairs Dept Williamsburg Incident Investigation 89-WM-2, in Response to 930810 Telcon ML20045G6991993-06-23023 June 1993 Forwards TS Change Request 54 to License DPR-4,including Facility Characterization as Activity Permissible in TS 1999-06-03
[Table view] |
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uE- SAXTON NUCLEAR EXPERIMENTAL CORPORATION GENERAL P U B LIC UTILITIES SYSTEM
=
Jersey Central Power & L!ght Company d Pennsylvania Electnc ComDany PE JC . Metropositan Edison Company MAILING ADDRESS; TELEPHONE.
I Upper Pond Rd. (201) 316-7000 Parsippany, NJ 07054 .,
SNEC-92-0002 MAR 31992 C301-92-0002 U. S. Nuclear Regulatory Commission Att: Document Control Desk Washington, DC 20555 Gentlemen:
Saxton Nuclear Pacility Operating-License No. DPR-4 Docket No. 50-146 Errata for SNEC Final Release Survey of the Reactor Support Buildings Report This submittal-provides errata for the subject report, as requested by A. Adams. The following changes should be made to the subject survey report:
- 1. Replace page 51 with the attached page 51.
- 2. Replace Appendix G with the attached Appendix G.
Please contact us if you require additional information. .
Sincerely,
- @ 0' 4hsc/ f.^j J. E. Hildebrand President, SNEC Attachments JEH/EP/ pip cc: A. Adams - NRC R. Bores - NRC M. Reilly - Commonwealth of PA J. Roth - NRC S. Weiss - NRC l
9203090209 920303 I !'
PDR ADOCK 05000146 P PDR f ERkATA.BAO
g-y, , e' A
- point measurements,. minimum,~ maximum, and average-dpm/100cm 2 for !
individual grids or survey _ blocks.
- 4. Removable Contamination Measurements _
The final survey results did not show any removable alpha or beta / gamma activity above the USNRC guidelines. All removablo alpha activity measurements were less than 20 dpm/100cm. d All i removable beta /gamraa activity measurements were less than 1000 dpm/100cm. 2 Greater than 99% of the smear results were less than-the minimum detectable activities for the instruments. The maximum alpha -smear was 10 dpm/100cm' and was most likely natural radioactivity. The maximum beta / gamma smear was 175 dpm/100cm.- 3 Minimum detectable concentrations averaged 7 dpm/100cm for alpha activity and 140 dpm/100cm* for beta / gamma activity. Tables-D-16 through D-17 in Appendix D contain the removable contamination measurements for individual grids or survey blocks.
5.- Gamma Exposure Rate Measurements The final survey results showed gamma exposure rates for all grids-were consistent with the guideline of 5 uR/hr above background measured at 1 meter from the surface. Measured exposure rates at meter were compared to the onsite instrument -background
~
1 .
measurements taken- for every survey. Ther onsite instrument background measurements ranged frou -4 uR/hr to 18 uR/hr. The raeasurements ranged from 0 uR/hr-to b uR/hr above background._ All onsite gamma exposure rates were within the variability of offsite background measurements-of 6 uR/hr to 22 uR/hr.
.f When exposure rate measurements were made on the outside walls and the RWST pad additional measures:were implemented to-reduce the shine f rom the surrounding soils. Soil was excavated along-the northwest wall of the RWDF building, along the north wall of-the RWDF pipe tunnel, and around the RWST pad and shielding was used to ensure that the structure being surveyed was the source of the exposure reading.
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e 4
APPENDIX G -
DISMANTLEMENT AND DEMOLITION PROCESS 6
m
- 701 -
t DISMANTLEMENT AND DEMOLITION PROCESS Upon issuance by the USNRC of the TSCR to remove the C&A, RWDF, FDSB, and RWST pad from Technical Specification contrals, each of the structures will be readied for dismantlement. It is SNEC's intent to restore the land to its original contour such that it sill have no impact upon the U.S. Army Corps of Engineers' flowage easement. There will be no regulated demolition landfill created.
Masonry material f rcm the demolition of structures to 3 f eet below grade will be used as backfill in the RWDF basement and the yard pipe tunnel. The backfilled Rh0F basement and yard pipe tunnel will be covered with a soil cap. Construction rebar and other non-masonry materials will be removed to the extent possible from the concrete prior to its use as backfill material. Other non-masonry materials f rom the buildings such as glass and roofing, will be removed to the extent possible. Excess concrete rubble that can not be used as backfill and other non-masonry materials will be disposed oO offsite in an approved landfill or recycled.
The filled drum storage bunker is an eartqen unit with wooden criboing. The interior wall consisting of the wood cribbing will be surveyed in accordance with procedures f or release of equipment.
If the wood cribbing meets USNRC guidelines for release it will be disposed of offsite in an approved landfill. The soil behind the wood may be used in conjunction with the masonry material to backfill in the RWDF and pipe tunnel. If used in this manner, the soil will be sampled and analyzed and shown to be consistent with the environmental pathways analysis.
All applicable dismantlement and demolition permits will be setured prior to the start of work. Demolition work will be conducted in a manner to minimize any environmental impact.
02 -
4
4 Appropriate . radiological and environmental -controls will .be 'in '
place throughout the dismantlem?nt and demolition process. Several areas were identified during the final release survey that were 5 inaccessible to survey instruments. These areas will be surveyed '
and dispositioned during dismantlement and demolition. Demolition ,
hold points have been identified to allow these additional surveys .,
to occur. The USNRC will be notified of the status of-each hold ,
point after each-has been surveyed. If the hold point meets USNRC ,
release guidelines, the USNRC will be given the option to review the results before final disposition. If thu hold point is considered- to be radwaste, it will be disposed of in accordance with procedures for radvaste. These hold points include: l 2
o walls behind tne electrical breaker boxes and emergency lighting fixtures (C&A and RWDF) -
o structural 1-beams in C&A o drain pipes off of the C&A roof o floors underneath groundwater collection containers (RWDF) o ceiling hatch in the RWDF Evap. Room
, o area underneath wooden frame " bridge" in the C&A pipe
- tunnel i o erea underneath groundwater collection pipes in the RWDF pipe tunnel o two pipes in RWDF Pump and Compressor doom ceiling o two pipes in RWDF Drum Shipping Room ,
l o. areas underneath any wooden-supports o several penetrations-in Yard Pipe Tunnel ceiling l
l- Radiological Controls technicians will provide- job coverage
- throughout the-dismantlement and demolition process. They will be instructed-to survey the hold points identified above as well- as any additional areas not previously surveyed that may become-accessible. If any areas / materials exceed the USNRC release l_ , - 704 -
'4--
4 4 '
Appropriate environmental monitoring will continue to be performed during the demolition process. <
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