ML20127F933
| ML20127F933 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 01/14/1993 |
| From: | Murley T Office of Nuclear Reactor Regulation |
| To: | Steinbring G CITIZENS AWARENESS NETWORK |
| References | |
| NUDOCS 9301210092 | |
| Download: ML20127F933 (3) | |
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UNITED STATES
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January 14, 1993 Hs. Gail D. Steinbring President Citizens Awareness Network P.O. Box 83 Shelburne Falls, Massachusetts 01370
Dear Ms. Steinbring:
I am responding to your letter of December 21, 1992, addressed to Chairman Selin, in which you expressed concern about issues regarding the Yankee Nuclear Power Station (Yankee), some of which you raised in your previous letter of November 2, 1992.
On December 29, 1992, the U.S. Nuclear Regulatory Commission (NRC) issued its response to your November 2 letter after carefully reviewing the issues you discussed.
The week before we received your December 21, 1992 letter, a re)resentative of the Citizens Awarenass Network (CAN) contacted the NRC by teleplone and requested that CAN be added to the NRC Service List; you also mentioned in your letter that you wanted to receive documents in a timely fashion. On December 15, 1992, the NRC added CAN to the NRC Service List for Yankee, in your letter you expressed concern about notification of the public on proposed exemptions.
For most exemptions that were issued to Yankee to date, the NRC, in accordance with 10 CFR Part 51 of the NRC regulations, published an Environmental Assessment (EA), prior to issuance of the exemptions.
However, exemptions related to insurance, indemnity or safeguards do not require an EA.
You will receive EAs in the future through the inclusion of CAN on the NRC Service List.
Documents issued by the licensee may be obtained from the local public document room (LPDR) in Greenfield, Ma:sachusetts. The manager of our LPDR Program has informed my staff that microfiche and microfiche address summaries will be available at the LPDR within 2 to 3 weeks after the NRC headquarters staff receives a submittal.
if you have access problems, you may call the LPDR Programs at NRC headquarters at 1-800-638-8081, a toll free number.
1 In your December 21, 1992 letter, you expressed a concern about exemptions issued by the NRC to Yankee for certain prcgrams at the plant, in our response to the November 2, 1992 letter, we discussed our bases for' issuing the emergency preparedness exemptions. We have also issued exemptions for containment leak testing, updates to the final safety analysis report, and the safeguards program.
You requested that we rescind all recently approved exemptions and halt reactor dismantling until a decommissioning plan is approved.
Before issuing these exemptions, the NRC performed extensive safety and environmental reviews to enrure that the reliefs maintained adequate levels of public health and safety and environmental protection. We considered the permanently shutdown and defueled status of the plant. The NRC has issued similar exemptions to the licensees for the Fort St. Vrain, RanchoSeco,andShorehamplantswhentheseplantswereinthesamephaseof)
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Ms. Gail D. Steinbring January 14, 1993 the decommissioning process as Yankee is now.
Your two letters do not contain any new information that would prompt us to reopen those reviews.
You also raised a coricern about the NRC signaling Yankee that it may begin dismantling the reactor and shipping highly radioactive components offsite.
While one of the components, the reactor internals, that Yankee wants to ship to a low-level waste disposal facility is " highly radioactive" it still qualifies as low-level waste.
Similar components have been shipped by Yankee and other licensees in the past, as have been steam generators.
With respect to licensee plans for removal of such components, the NRC staff has requested in its letter of December 15, 1992, and in the meeting summary of December 23, 1992, more detailed information about the proposed licensee activities in this area.
Both documents are enclosed.
The information requested from the licensee includes an analysis of pre-decommissioning activities to demonstrate that they are within the bounds of the NRC final Generic Environmental Statement and an evaluation of how the proposed component removal process would nct preclude deconmissioning alternatives nor future unrestricted site access.
In your second letter you reemphasized your desire for a public hearirig on decommissioning issues at Yankee.
We plan to have a public meeting in the local area when we have received the requested information.
The NRC project manager will keep you apprised our plans for this meeting.
My staff is available to discuss these or other concerns that you may have.
You may contact Morton B. fairtile, the NRC Project Manager fcr this facility, at (301) 504-1442.
Sincerely, W e_._[/N((A
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Thomas E. Murley, Direc or Office of Nuclear Reactor Regulation
Enclosures:
1.
NRC Letter of December 15, 1992 2.
Meeting Summary of December 23, 1992
l Hs Gail D. Steinbring January 14, 1993 the decommissioning process as Yankee is now.
Your two letters do not contain any new information that would prompt us to reopen those reviews.
You also raised a concern about the NRC signaling Yankee that it may begin dismantling the reactor and shipping highly radioactive components offsite.
While one of the components, the reactor internals, that Yankee wants to ship to a low-level waste disposal facility is " highly radioactive" it still qualifies as low-level waste.
Similar components have been shipped by Yankee and other licensees in the past, as have been steam generators.
With respect to licensee plans for removal of such components, the NRC staff has requested in its letter of December 15, 1992, and in the meeting summary of December 23, 1992, more detailed information about the proposed licensee activities in this area.
Both documents are enclosed.
The information requested from the licensee includes an analysis of pre-decommissioning activities to demonstrate that they are within the bounds of the NRC Final Generic Environmental Statement and an evaluation of how the proposed component removal process would not preclude decommissioning alternatives nor future unrestricted site access.
In your second letter you reemphasized your desire for a public hearing on decommissioning issues at Yankee. We plan to have a public meeting in the local area when we have received the requested information.
The NRC project manager will keep you apprised of our plans for this meeting.
My staff is available to discuss these or other concerns that you may have.
You may contact Morton B. Fairtile, the NRC Project Manager for this facility, at (301) 504-1442.
origjnal slened by Sincerely, hI. Earley Thomas E. Murley, Director Office of Nuclear Reactor Regulation
Enclosures:
1.
NRC Letter of December 15, 1992 2.
Meeting Summary of December 23, 1992 DISTRIBUTION:(STEIN 02.MBF) (Action diskette-lb)
Docket File No.50-029 TMurley/fMiraglia OPA OGA ONDO R/F JPartlow HFairtile Region I DORS R/f BGrimes JLieberman EHylton PDRs SWeiss TMartin, RI RBernero JTaylor ED0 R/F WHohl, RI WRussell JSniezek.
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8 9 l W ASHING T ON. D. C. 20p6 December 15, 1992 Docket No.50-029 Dr. Andrew C. Kadak, President l
and Chief Executive Officer t
Yankee Atomic Electric Company 580 Main Street Bolton, Massachusetts 01740-1398
Dear Dr. Kadak:
SUBJEC1: COMPONENT REMOVAL ACTIVITIES AT THE YANKEE NUCLEAR POWER STATION 1
1_ am responding to your letter of November 25 1992, addressed to Dr. Murley, in which you outlined Yankee Atomic's program,to remove and dispose of
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radioactive components at your facility prior to NRC approval of your-decommissioning plan.
As you are aware, the Commission has these issues under current review and we anticipate that the Commission will provide guidance in this area. At the public meeting held on December 8, 1992, our staffs discussed these issues and de provided questions to your staff regarding your proposed pre-decommissioning activities. These questions will be included in our'.
meeting summary of the December 8,1992 meeting which will be issued shortly.
We understand that you plan to respond to our questions prior to any removal of large components or structures.
Sincerely.
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Brian K. Grimes, Director i
Division of Operating Reactor Support Office of Nuclear Reactor Regulation cc:
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December 23, 1992 Docket No. 50 029 LICENSEE: YANKEE AT0Hlc ELECTRIC COMPANY FACILITY:
YANKEE NUCLEAR POWER STATION
SUBJECT:
MEETING
SUMMARY
- DISCUSSION OF PROPOSED SITE WORK UNDER 10 CFR 50.59 PRIOR TO NRC APPROVAL OF DECOMMISSIONING PLAN On Tuesday, December 8, 1992, the licensee, at their request, came in for a meeting at the NRC headquarters in Rockville, Maryland to discuss the subject topic.
The meeting, primarily, was a presentation by the licensee covering the following agenda:
Activities in Progress implementation of Changes Interaction with NRC Access to Funds The licensee used the enclosed set of slides (Enclosure 1) in the presentation.
James Partlow, NRR Associate Director for Projects, opened the meeting by stating that the work the licensee may perform prior to staff approval of the Decommissioning Plan (0-Plan) is still under policy review and development by the Commission.
The licensee is planning to remon, prior to approval of the D-Plan, the following components under the provisions of 10 CFR 50.59:
the reactor pressure vessel internals, the four steam generators, and the pressurizer.
The staff requested that the sollowing sdditional information be submitted to, the NRC:
(1)
An analysis of pre-decommissioning activities demonstrating that the environmental impacts of such activities, when integrated with planned decommissioning activities, are within the bounds of the
" Final Generic Environmental Impact Statement," published by the NRC in August 1988 as NUREG-0586.
(2)
An evaluation of how the proposed component removal process under 10 CFR 50.59 would not preclude decommissioning alternatives, including the objective of future unrestricted access to the site.
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A letter providing data on future facility staff size ano staff qualifications, in particular Health Physics staff and Management staff.
(4)
A detailed description of the design change (EDCR) method, and the ALARA (radiation protection) program.
(5)
Plans and schedules for site work proposed prior to approval of the D-Plan and the funding plan to cover this interim site work (including cost estimates).
An attendance list is provided as Enclosure 2.
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Morton B. Fairtile, Senior Project Manager Non-Power Reactors and Decommissioning Project Directorate Division of Operating Reactor Support Office of Nuclear Reactor Regulation
Enclosures:
As stated cc w/ enclosures:
See next page l
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Hs. Jane H. Grant Yankee Rowe Docket No. 50-29 cc:
Dr. Andrew C. Kadak, President Mr. David Rodham, Director and Chief Executive Office ATTN:
Mr. James B. Muckerheide Yankee Atomic Electric Company Massachusetts Civil Defense Agency b80 Main Street 400 Worcester Road Bolton, Massachusetts 01740-1398 P. O. Box 1496 Framingham, Massachusetts 01701-0317 Thomas Dignan, Esq.
Ropes and Gray Chairman, Franklin County One International Place Commission Boston, Massachusetts 02110-2624 425 Main Street Greenfield, Massachusetts 03101 Mr. N. N. St. Laurent Plant Superintendent Executive Director Yankee Atomic Electric Company New England Conference of Public Star Route Utility Commissioners Rowe, Massachusetts 01367 45 Memorial Circle Augusta, Maine 04330 Resident inspector Yankee Nuclear Power Station Citizens Awareness Network U.S. Nuclear Regulatory Commission P. O. Box 83 P. O. Box 28 Shelburne Falls, Massachusetts 01370 Honroe Bridge, Massachusetts 01350 Regional Administrator, Region i U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, Pennsylvania 19406 Robert H. Hallisey, Director Radiation Control Program Massachusetts Department of Public Health 305 South Street Boston, Massachusetts 02130 Commissioner Richard P. Cedano Vermont Department of Public Service 120 State Street, 3rd Floor Montpelier, Vermont 05602 Hr. Jay K. Thayer Vice President and Manager of Operations Yankee Atomic Electric Company 580 Main Street Bolton, Massachusetts 01740-1398 1
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FACILITY RADIOLOGICAL STATUS
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l IMMEDIATE DISMANTLEMENT IS PREFERRED OVER SAFSTOR WHY IMMEDIATE DISMANTLEMENT?
e REMOVES FUTURE COST UNCERTAINTY, ESPECIALLY LLW DISPOSAL REMOVES RADI0 ACTIVITY FROM THE SITE AS S00N AS POSSIBLE, FREEING SITE FOR OTHER USES REPRESENTS LEAST COST OPTION ELIMINATES LONG TERM SURVEILLANCE AND ENVIRONMENTAL MONITORING i
BEST OPTION FOR SINGLE ASSET UTILITY MAXIMIZES USE OF EXPERIENCED STAFF FINAL GENERIC ENVIRONMENTAL IMPACT STATEMENT e
SAFSTOR/DECON COMPARIS0N BOTH DECON AND SAFSTOR ARE " REASONABLE OPTIONS FOR DECOM4ISSIONING LIGHT WATER POWER REACTORS" HIGHER DECON OCCUPATIONAL EXPOSURE HAS " MARGINAL SIGNIFICANCE TO HEALTH AND SAFETY" DECON OCCUPATIONAL EXPOSURE SIMILAR TO " ROUTINE ANNUAL DOSE FROM PLANT OPERATIONS"
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YAf\\ (EE DECOVVISSIONill\\G OVERVIEW SHUTDOWN PRE-DECOMMISSIONING SAFSTOR
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NO UNREVIEWED SAFETY QUESTION PER 10 CFR.-50.59 SAFETY EVALUATION i
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SHORT TERM ACTIONS e
'NEEDED TO CONTINUE YANKEE'S EFFORTS TO PRESERVE I
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-ENCOURAGE NRR/NMSS REVIEWERS TO VISIT YANKEE PLANT PRIOR AND DURING REVIEW 0F DECOMMISSIONING PLAN e
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QUALITY-ASSURANCE 50.59 PROCESS-i l
e FOCUS ON ISSUES IMPORTANT TO PUBLIC HEALTH AND SAFETY, SUCH AS SITETCHARACTERIZATION, FINAL SURVEY
Yankee Atomic Meetina List of Attendees December 8. 1992 Name Oraanization Jim Partlow NRCINRR Associate Director Mort Fairtile NRRfDORS/0NDD L. Cunningham NRR/PRPB Bob Wood NRR/ILPB Stewart Brown NRR/0NDD Dan O'Neal NRR/0NDD Pete Erickson NRR/0NDD Richard Dudley NRC/NRR Larry Bell NRR/NMSS John Austin NRR/NMSS Ed Reis NRC/0GC Joseph Nick NRC/ Reg 1/DRSS/FRPS Neil Perry NRC Region I SRI Yankee Rowe H. T. Tracy Jr.
Yankee Atomic J. K. Thayer Yankee Atomic Russell A. Mellor Yankee Atomic K. J. Heider Yankee Atomic Jane M. Grunt Yankee Atomic Patrick Sheldon Yankee Atomic Theresa Meisenheimer Bechtel/SERCH Judith Sikorski Bechtel/SERCH Gene Gena Winston & Strawn ENCLOSURE 2
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