ML070310208

Public Meeting on Indian Point Nuclear Station, Unit 1 Decommissioning

ML070310208
Person / Time
Site:	Indian Point
Issue date:	01/20/1999
From:	Minns J Entergy Nuclear Operations
To:	NRC/FSME
References
FOIA/PA-2007-0060
Download: ML070310208 (29)

Text

PUBLIC MEE7TING (h)/%T lAT71TA JL.LV~lzlu AT7DIAr~

"IJI VI NUCLEAR STATION, UNIT 1 DECOMMISSIONING Peekskill, New York John L. Minns Project Manager CJ\l(

AGENDA INDIAN POINT NUCLEAR STATION , UNIT 1 DECOMMISSIONING STATUS MEETING JANUARY 20, 1999 6:30-7:00 pm Sign in for member of the public.

7:00- 7:10 pm Introductory remarks Francis Cameron NRC 7:10-7:30 pm NRC's Regulatory Framework for Nuclear Power Reactors.

John Minns, NRC 7:30-7:45 pm Questions and Answers on regulatory framework.

7:46-8:15 pm Status of Indian Point Unit I Facility and future plans for completing decommissioning of the facility.

A. Allen Blind, James S. Baumstark Consolidated Edison 8:15-8:30 pm Questions and Answers on status of Indian Point 1.

8:30-8:45 pm NRC inspection oversight Ronald Bellamy, Anthony Dimitriades, NRC 8:45-9:00 pm Questions and Answers on inspection oversight.

9:00pm Questions and Answers on any remaining issues.

10:00 pm ADJOURN

United States Nuclear Regulatory Commission PUBLIC MEETING ON INDIA N POINT NUCLEAR S TA TION1 UNIT 1 DECOMMISSIONING Non-Power Reactor and Decommissioning Project IDirectorate Division of Reactor Program Management January 20, 1999 Peekskill, New York John L.Minns Project Manager

'I

PUBLIC MEETING ON INDIA N POINT NUCLEAR S TA TION UNIT I Office of Nuclear Reactor Regulation NRC Staff Present Office of Nuclear Reactor and Regulation Region I Dr. Seymour H. Weiss, Director, Dr. Ronald Bellamy, Chief Non-Power Reactor and Decommissioning Decommissioning arid Laboratory Directorate Branch, NMSS Dr. Michael T. Masnik, Section Chief Ms. Etoy G. Hylton, Licensing Assistant Mr. Anthony Dimitriades, Health'Physicist Mr. John Minns, Project Manager Decommissioning arid Laboratory Mr. Phillip M. Ray, Project Manager Branch, NMSS Mr. Dino C. Scaletti, Sr. Project Manager Ms. Diane P. Screnci, Public Affairs Office!.r Mr. William D. Huffman, Project Manager Office of the General Counsel Office of Nuclear Materials Safety

& Safeguards Ms. Ann.P. Hodgdon, Senior Attorney Mr. Timothy Johnson, Chief Facility, LLW, NMSS Mr. Francis X. Cameron, Deputy Assistant 'V General Counsel and Special Counsel for Public Liaison 2

DECOMMISSIONING OVERVIEW What is decommissioning?

Decommissioning is, the removal of a facility safely from (service and the reduction of residual radioactivity to a level that permits release Of the property and termination of the license.

What is NOT decommissioning

• Non-radio logical demolition.

• Site restoration activities.

/

• Spent fuel management and funding.

3

DECOMMISSIONING OVER ViEWý (CONTINUED)

NRC Process and Focus Overview

• NRC focus is on removal of radiological hazards

• First step is to remove facility safely from service

• Utility reduces levels of radioactive material on site

• Utility performs detailed final radiation survey

• NRC may perform confirmatory survey

• If release criteria are met, license is terminated 'i

• NRC oversight ends 4

• DECOMMISSIONING ALTERNAL TI VESS Utility has a choice of decommissioning alternatives

• Dismantlement and decontamination (DEC ON)

• Safe storage (SAFSTOR) for up to 60 years

• Combination of DECON and SAFSTOR NRC has found these alternatives acceptable as long as the regulations are followed

• Risk to the public from decommissioning is significantly reduced from when the facility was in operation

• Regulatory requirements are reduced from those for an operating plant 5

POST-SHUTDOWN DECOMMISSIONING ACTIVITIES REPORT (PSDAR)

The PSDAR is required to provide:

• Description of planned decommissioning activities

• Schedule for accomplishment of planned activities

• Estimate of expected costs

• Reasons for concluding that environmental impacts are bounded by previously issued environmental impact statements The NRC staff will hold a public meeting in the vicinity of, the site.

PURPOSE OF PSDAR SUBMITTAL

• Inform the public of the utility' s plans for decommissioning

• Allow the NRC to conduct inspections prior to the inlitiation of major decommissioning activities.

• Allow NRC staff to budget and allocate resources fo~r decommissioning inspections.

• Requires the utility to reexamine financial resources for decommissioning before any major activities are conducted.

• Requires the utility to evaluate the potential environrncnta1 impacts associated with planned decommissioning activities against existing environmental statements.

7

ADDITIONAL RESTRICTIONS The utility is prohibited from performing any decommissioning activity that:

• Forecloses the release of the site for possible unrestricted use; or

• Results in significant environmental impacts not previously considered; or

• Results in there no~longer being reasonable assurance that adequate funds will be available.

i 8

LICENSE TERMINA TION PlAN The plan will describe:

• Site characterization

• Identification of remaining dismantlement activities

• Plans for site remediation

• Detailed plans for the final radiation survey

• Description of the end use of the site, if restrictions are impo~sed

• Updated site-specific cost estimate of remaining decommarissioning costs

• Supplement to the Environmental Report describing any new information or significant change associated with the utility's termination activities.

9

License Termination Plan (continued)

• Plan receipt will be noticed in the Federal Register and the plan will be made available for public comment

• Opportunity for a hearing on the plan will be given

• NRC will hold a public meeting

• The plan will be approved by issuance of a license amiendment

• Utility continues to decommission the site and perform a site radiation survey

• NRC may perform a confirmatory survey(s)

• The license is terminated if the license termination plan was followed and the site meets the release criteria 10

Decommissioning Experience-9 2 Power reactors have completed decommissioning

• Shoreham & Fort St. Vrain 18 power reactors are in decommissioning;

• 6 facilities are being decontaminated and dismantled: 'Trojan, Yankee Rowe, Big Rock Point, Haddam Neck, Maine Yankee

• 10 facilities are in long-term storage: TMI-2, Dresden 1, Fermi 1, VBWR, La Crosse, Peach Bottom 1, Rancho Seco, San Onofre 1,.

Indian Point 1, Humboldt Bay 3

• 2 facilities planning long term storage: Zion 1 and 2 I facility permanently shutdown, undecided, Millstone. Unit 1I I1I

POINTS OF CONTACT

• Licensing

• Inspections U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission ATTN: JOHN L. MINNS ATTN: DR. RONALD BELLAMY Washington, DC 20555-000 1 472 Allendale Road King of Prussia, PA 199406-14 15 Telephone: (800) 368-5642 Telephone: (800) 432-1156 E-Mail: JLM3 @NRC.GOV if 12

REACTOR DECOMMISSIONING STATUS SHUTDO IYV PO WER REA CTORS Thermal Fuel1 Reactor Type Power Location Shutdown Status COnsite Indian Point 1 PWR 615 MW Buchanan NY 10/31/74 SAP STOR Yes Dresden 1 BWR 700 MW Morris 11 10/31/78 SAFSTOR Ye Fermi 1 Fast Breeder 200 MW Monroe Co. MI 9/22/72 SAFSTOR No GE VBWR BWR 50 MW Alameda Co. CA 12/9/63 SAFSTOR No Yank ee Rowe PWR 600 MW Franklin Co. MA 10/1/91 DECON Yes Big Rock Point BWR 67 MW Charlevoix MI 8/29/97 DECON Yes Humboldt Bay 3 BWR 200 MW Eureka CA 7/02/76 SAFSTOR Yes.

Peach Bottom 1 HTGR 115 MW York Co. PA 10/31/74 SAFSTOR No San Onofre 1 PWR 1347 MW San Clemente CA 11/30/92 SASO es, Millstone BWR 201 1 MW Waterford, CT 7/21/98 Undecided Yes IV 13

REA CTOR DECOMMISSIONING STA TUS SHUTD 0 WV PO WER REA CTORS (CONTINUED)

Thermal Fuel Reactor Type Power Location Shutdown Status 0Onsite H-addam Neck PWR 1825 MW Haddam Neck CT 7/22/96 DECON Y es, Fort St. Vrain HTGR 842 MW Platteville CO 8/18/89 License Yes Terminated Zion 1 PWR 3250 MW Zion IL 2/21/98 SAFSTOR Yes Zion 2 PWR 3250 MW Zion IL 2/21/98 SAFSTOR Yes Maine Yankee PWR 2772 MW Bath ME 12/6/96 DECON Yes:

Rancho Seco PWR 2772 MW Sacramento CA 6/7/89 SAFSTOR 'Yes Three Mile PWR 2772 MW Middletown PA 3/28/79 SAFSTOR* No Island Shoreham BWR 2436 MW Suffolk Co. NY 6/28/89 License No Terminated Trojan PWR 3411 MW Portland OR 11/9/92 DECON Yes i LaCrosse BWR 165 MW LaCrosse WI 4/30/87 SAFSTOR Yes 14

Enclosure 2 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 December 8, 1998 M EmORANU-M TO: Sey mo ur H. We iss-, Dbire ctior Non-Power Reactors and Decommissioning Project Directorate .-

-Division of Reactor Program Managee erdt, NRRR FROM: John L. Minns, Project Manager Non-Power Reactors and Decommis I P~roject Direc-torate Division of Reactor Program Management, NRR

SUBJECT:

FORTHCOMING PUBLIC MEETING CONCERNING THE DECOMMISSIONING OF INDIAN POINT NUCLEAR GENERATING STATION, UNIT 1 DATE & TIME: Wednesday, January 20, 1999 7:00 p.m. - 9:30 p.m.

LOCATION: New York State Armory, 955 Washington Street, Peekskill, NY PURPOSE: To inform the public of the licensee',s plans for decommissioning the Indian Point Nuclear Generating Station Unit 1. The NRC staff will present information regarding the decommissioning regulations and inspections oversight of the facility. The licensee (Consolidated Edison Company) will present information regarding their planned decommissioning activities. Following the presentations, the public will have an opportunity for questions and comments. The meeting will be transcribed by a cour-t reporter.

The public meeting agenda is attached. Francis X. Cameron, Deputy Assistant General Counsel and Special Counsel for Public Liaison, NRC will host the meeting.

PARTICIPANTS: NRC Consolidated Edison J. Minns A. Hodgdon A. A. Blind M. Masnik R. Bellamy S. Weiss Docket No.50-003

Attachment:

As stated cc w/attachment: See Next page CONTACT: John Minns, NRR/PDND (301) 415-3166

• Meetings between NRC technical staff and applicants or licensees are open for interested members of the public, petitioners, intervenors, or other parties to attend as observers pursuant to "Commission Policy Statement on Staff Meetings Open to the Public" 59 Federal Register 48344, 9/20/94.

1998 (Volume 63, Number 236)]

[Notices]

rPa-e-67940-n-From the Federal Register Online via GPO Access [wais. access.gpo. gov]

[DOCID:frO9de98-1 211 NUCLEAR REGULATORY COMMISSION

[Docket N50-03 Consolidated Edison Company; Indian Point Nuclear Generating Station, Unit 1; Notice of Public Meeting The NRC will conduct a public meeting at the New York State Armory, 955 Washington Street, Peekskill, New York 10566-5815, on January 20, 1999, to discuss plans developed by Consolidated Edison Company (Con Edison) to decommission the Indian Point Nuclear Generating Station Unit 1. The Indian Point Station, located in Buchanan, New York, includes the permanently shutdown Unit 1 and two operating units. Unit 2 is operated by Consolidated Edison Company, and Unit 3 by New York Power Authority. The meeting is scheduled for 7:00--9:30 p.m., and will be chaired by Mr. Francis X. Cameron, Deputy Assistant General Counsel and Special Counsel for Public Liaison, NRC. The public meeting is being held pursuant to the NRC's regulations in Title 10 of the Code of Federal Regulations, Section 50.82(a)(4) regarding the requirements of a public meeting on the licensees plans for decommissioning the facility as described in the post-shutdown decommissioning activities report (PSDAR). Con Edison submitted a decommissioning plan, which was approved by the NRC in January 1996, prior to the rule change promulgated at 61 FR 39301 (July 29, 1996), requiring a PSDAR.

Decommissioning plans approved prior to the revision are considered to meet the requirement for a PSDAR and are subject to the revised regulations, including the requirement for a public meeting. The meeting Will include a presentation by the NRC staff on the decommissioning process and NRC programs for regulatory oversight of decommissioning activities. There will also be a presentation by Consolidated Edison Company on planned decommissioning activities.

There will be an opportunity for members of the public to ask questions of NRC staff and Con Edison representatives and make comments related to decommissioning of Indian Point Unit 1. The meeting will be transcribed.

Con Edison's decommissioning plan provides a short discussion of the plant history, a description of the unit's radiological conditions, and a description and schedule of planned decommiissionirng activities.

This decommissioning plan and the NRC's safety evaluation associated

2 with the plan is available for public inspection at the White Plains Public-Library, 100 Martine-A enueAWhite-Plains-, NY 10601. For- more information contact John L. Minns, Non-Power Reactors and Decommissioning Project Directorate, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; telephone 301-415-3166. -

Dated at Rockville, Maryland, this 3rd day of December 1998.

ruoL tII ie I"Au c; e rR e gu 1at0LLJI 0M n iis s.UI oIU n.

Seymour H. Weiss, Director, Non-Power Reactors and Decommissioning Project Directorate Division of Reactor Program Management, Office. of Nuclear Regulatory Regulation.

[FR Doc. 98-32634 Filed 12-8-98; 8:45 am]

BILLING CODE 7590-01-P

C1 ptREQ;(

UNITED STATES -

0 NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 December 28, 1998 The Honorable Sandra F. Galef New York State Assemblywoman

-Albany -and Ossining, New- York-District Office: 2 Church Street Ossining, New York 10562

SUBJECT:

PUBLIC MEETING CONCERNING THE DECOMMISSIONING OF INDIAN POINT NUCLEAR GENERATING STATION, UNIT 1

Dear Ms. Galef:

'The U.S. Nuclear Regulatory Commission (NRC) invites you to attend and participate in the upcoming public meeting at the New York State Armory, 955 Washington Street, Peekskill, New York, beginning at 7:00 p.m., on January 20, 1999. The meeting will include a presentation by the NRC staff on the decommissioning process and NRC programs for regulatory oversight of decommissioning activities. There will also be a presentation by Consolidated Edison Company on planned decommissioning activities. There will be an opportunity for members of the public to ask questions of NRC staff and Con Edison representatives and make comments related to decommissioning of Indian Point Unit 1.

The meeting will be transcribed. Detailed information is provided in the Federal Register

.Notice (Enclosure 1) and the meeting notice (Enclosure 2). For more information, please contact John L. Minns, the NRC Project Manager for Indian Point, Unit 1, at (301) 41 5-3166.

Thanks for your interest.

Sincerely, Dr. Seymour H. Weiss, Director Non-Power Reactors and Decommissioning Project Directorate Division of Reactor Program Management Office of Nuclear Reactor Regulation Docket No.50-003

Enclosures:

As stated

REG 0p`%

UNITED STATES NUCLEAR REGULATORY COMMISSION 0 WASHINGTON, D.C. 20555-0001

? December 28, 1998 The Honorable Frances S. Gibbs Mayor of Peekskill--

840 Main Street Peekskill, New York 10566 PU1 0BL rU VtC RA EE I IK4 '~ ~u I I...l4LI- ----

is .ý. - ... N.N

...- OF

-. l.fA

..-. . P INT NUCLEAR GENERATING STATION, UNIT 1

Dear Ms. Gibbs:

The U.S. Nuclear Regulatory Commission (NRC) invites you to attend and participate in the upcoming public meeting at the New York State Armory, 955 Washington Street, Peekskill, New York, beginning at 7:00 p.m., on January 20, 1999. The meeting will include a presentation by the NRC staff on the dlecommissioning process and NRC programs for regulatory oversight of decommissioning activities. There will also be a presentation by Consolidated Edison Company on planned decommissioning activities. There will be an opportunity for members of the public to ask questions of NRC staff and Con Edison representatives and make comments related to decommissioning of Indian Point Unit 1.

The meeting will be transcribed. Detailed information is provided in the Federal Register Notice (Enclosure 1) and the meeting notice (Enclosure 2). For more information, please contact John L. Minns, the NRC Project Manager for Indian Point, Unit 1, at (301) 41 5-31)66.

Thanks for your interest.

Sincerely, Dr. Seymour H. Weiss, Director Non-Power Reactors and Decommissioning Project Directorate Division of Reactor Program Management Office of Nuclear Reactor Regulation Docket No.50-003

Enclosures:

As stated

UNITED STATES NUCLEAR REGULATORY COMMISSION z WASHINGTON, D.C. 20555-0001 December 28, 1998 The Honorable Alfred J. Donahue Mayor of Buchanan Municipal Building Tate Avenue Buchanan, New York 10511

SUBJECT:

PUBLIC MEETING CONCERNING THE DECOMMISSIONING OF INDIAN POINT NUCLEAR GENERATING STATION, UNIT I

Dear Mr. Donahue:

The U.S. Nuclear Regulatory Commission (NRC) invites you to attend and participate in the upcoming public meeting at the New York State Armory, 955 Washington Street, Peekskill, New York, beginning at 7:00 p.m., on January 20, 1999. The meeting will include a presentation by the NRC staff on the decommissioning process and NRC programs for regulatory oversight of decommissioning activities. There will also be a presentation by Consolidated Edison Company on planned decommissioning activities. There will be an opportunity for members of the public to ask questions of NRC staff and Con Edison representatives and make comments related to decommissioning of Indian Point Unit 1.

The meeting will be transcribed. Detailed information is provided in the Federal Register Notice (Enclosure 1) and the meeting notice (Enclosure 2). For more information, please contact John L. Minns, the NRC Project Manager for Indian Point, Unit 1, at (301) 415-3166.

Thanks for your interest.

Sincerely, Dr. Seymour H. Weiss, Director Non-Power Reactors and Decommissioning Project Directorate Division of Reactor Program Management Office of Nuclear Reactor Regulation Docket No.50-003

Enclosures:

As stated

I.

REQ&p 4 UNITED STATES REGULATORY COMMISSION C0 z NUCLEARWASHINGTON, D.C. 20555-0001 December 28, 199.8 Ms. Linda D. Puglisi Town Supervisor Cortlandt Towvn Hall 1 Heady Piace Cortlandt Manor, New York 10566

SUBJECT:

PUBLIC MEETING CONCERNING THE DECOMMISSIONING OF INDIAN POINT NUCLEAR GENERATING STATION, UNIT 1

Dear Ms. Puglisi:

The U.S. NuclearRegulatory Commission (NRC) invites you to attend and participate in the, upcoming public meeting at the New York State Armory, 955 Washington Street, Peekskill, New York, beginning at 7:00 p.m., on January 20, 1999. The meeting will include a presentation by the NRC staff on the decommissioning process and NRC programs for regulatory oversight of decommissioning activities. There-will also be a presentation by Consolidated Edison Company on planned decommissioning activities. There will be an opportunity for members of the public to ask questions of NRC staff and Con Edison representatives and make comments related to decommissioning of Indian Point Unit 1.

The meeting will be transcribed. Detailed information is provided in the Federal Register Notice (Enclosure 1) and the meeting notice (Enclosure 2). For more information, please contact John L. Minns, the NRC Project Manager for Indian Point, Unit 1, at (301) 4 I 5-31 66.

Thanks for your interest.

Sincerely, Dir.eymour H. Weiss, Director Non-Power Reactors and Decommissioning Project Directorate Division -of Reactor Program Management Office of Nuclear Reactor Regulation Docket No.50-003

Enclosures:

As stated

TIP:24 -- Decommissioning Nuclear Power Plants Technical Issues Index INews and Information INRC Home

Background

Decommissioning is defined as the safe removal of a facility from service and reduction of residual radioactivity to a level that permits release of the property for unrestricted use and termination of the'license. When a licensee announces its decision to permanently close their nuclear power plant, decommissioning must occur. The licensee's decisions are based on economic and technical considerations. Some facilities have begun decommissioning before their operating licenses expired and earlier than originally anticipated. Decommissioning highlights for individual plants are presented in Tables 1 and 2.

Discussion Decommissioning involves three different alternatives: DECON, SAFSTOR, or ENTOMB.

Under DECON (immediate dismantlement), soon after the nuclear facility closes, equipment, structures, and portions of the facility containing radioactive contaminants are removed or decontaminated to a level that permits release for unrestricted use and termination of the license.

Under SAFSTOR, often considered "delayed DECON," a nuclear facility is maintained and monitored in a condition that allows the radioactivity to decay; afterwards, it is dismantled.

Under ENTOMB, radioactive contaminants are encas ed in a structurally sound material such as concrete and appropriately maintained and monitored until the radioactivity decays to a level

permitting unrestricted release of the property.

To be acceptable, decommissioning must be completed within 60 years. A time beyond that will be considered only when necessary to protect public health and safety in-accordance-with Nuclear Regulatory Commission (NRC) regulations.

Regulations The procedure for decommissioning a nuclear power plant is set out principally in NRC regulations 10 CFR Parts 50.75, 50.82, 51.53, and 51.95. In August 1996, a revised rule went into effect that redefines the decommissioning process and requires licensees to provide the NRC with early notification of planned decommissioning activities. The rule allows no major decommissioning activities to be undertaken until after certain information has been provided to the NRC and the public.

Several opportunities are provided for public involvement during the decommissioning process. The NRC must hold a meeting in the vicinity of the plant to discuss the decommissioning process and to listen to public comments. Proposed changes to the plant license and decommissioning activities that could adversely impact the public require NRC review and approval of a license amendment, which provides an opportunity for a public hearing. Additionally, a licensee's termination plan must be approved by license amendment, thus providing another hearing opportunity for affected members of the public. The requirements for decommissioning follow.

Within 30 day's after a nuclear power plant licensee decides to cease operations permanently, the licensee must submit a written certification to the NRC. When the licensee per manently removes radioactive nuclear fuel from the reactor vessel, the licensee must submit another written certification to the NRC. When NRC receives these certifications, the licensee loses its authority to operate the reactor or load fuel into the reactor vess-el. This reduces the licensee's annual fee and eliminates the obligation to

adhere to certain requirements needed only during reactor operation.

Within two years after submitting the certification of permanent closure, the licensee must submit a post-shutdown decommissioning activities report (PSDAR) to the NRC. This report must provide a description of the licensee's planned decommissioning activities, along with a schedule for accomplishing I Lne expectedI..costs. 'he. rl QrA E5 trenn, aiiu anesi rnaltdL ofth V A ILU UUL. II _2Px is required to discuss the-reasons for concluding that environmental impacts associated with the site-specific decommissioning activities have already been addressed in previous environmental reports. Otherwise, the licensee has to request a license amendment for approval of the activities and submit to the NRC an' environmental report on the additional decommissioning impacts.

After receiving a PSDAR, the NRC publishes a notice of receipt, makes the PSDAR available for public review and comment, and holds a public meeting in the vicinity of the plant to discuss the licensee's intentions.

Ninety days after the NRC receives the PSDAR, and generally 30 days after the public meeting, the licensee can begin major decommissioning activities without specific NRC approval. These activities could include permanent removal of such major components as the reactor vessel, steam generators, large piping systems, pumps, and valves..

However, decommissioning activities conducted without specific prior NRC approval must not:

foreclose release of the site for possible unrestricted use, result in, there being no reasonable assurance that adequate funds will be available for decommissioning, cause any significant environmental impact not previously reviewed.

I I I I 4

If any decommissioning activity does not meet these terms, the licensee is- r~qiired -to s~ubmit a license amendment request, which would provide an opportunity for a public hearing.

Initially-, the licensee can use up to three percent of the amount specified in NRC's regulations (10 CFR Part 50.75) for decommissioning without prior NRC approval. An additional 20 pe reet can 'we useud 910 days after s ubm ittal of th e rPui-AR'.

The remaining decommissioning trust funds are then available when the licensee submits a detailed site-specific cost estimate to the NRC.

Rulemaking A proposed rule, entitled "Safeguards for Spent Nuclear Fuel or High-Level Radioactive Waste," addresses physical protection requirements for the storage of spent fuel and high level radioactive waste in a permanently shutdown reactor, independent spent fuel storage installation (ISFSI), monitored retrievable storage installation, or a geologic repository. The Commission is reviewing policy aspects of ISFS1 safeguards before any further action is taken on the proposed rule. Significant revisions to the rule will be subject to public comment.

A proposed rule on nuclear power reactor decommissioning financial assurance implementation requirements was issued in September 1997 to reflect conditions expected from deregulation of the electric power industry. Among other things, this rule proposes requiring nuclear power plant licensees to report to NRC on the status of their decommissioning funds at least once every two years and annually within five years of the planned end of plant operation.

Other rulemakings that are anticipated include: a revision of regulations to address indemnity issues as a function of spent fuel pool -cooling per iods, site-specific decommissioning cost requirements based on actual data, and funding.

NRC PRINCIPLES Of 4 1 1 1 GOOD REGULATION INDEPENDENT Nothing but the highest possible standards of ethical performance and professionalism should influence regulation. However, independence does

-not imply isolation. AIl-available facts and- opinions m-ust be~ souight-openly from licensees and other interested members of the public. The many and possibly conflicting public interests involved must be considered. Final decisions must be based on obiective, unbiased assessments of all information, and must be documented with reasons explicitly stated.

OPEN Nuclear regulation is the public's business, and it must be transacted publicly and candidly. The public must be informed about and have the opportunity to participate in the regulatory processes as required by law.

Open channels of communication must be maintained with Congress, other government agencies, licensees, and the public, as well as with the international nuclear community.

EFFICI ENT The American taxpayer, the rate-paying consumer, and licensees are all entitled to the best possible management and administration of regulatory activities. The highest technical and managerial competence is required, and must be a constant agency goal. NRC must establish means to evaluate and continually upgrade its regulatory capabilities. Regulatory activities should be consistent with the degree of risk reduction they achieve. Where several effective alternatives are available, the option which minimizes the use of resources should be adopted. Regulatory decisions should be made without undue delay.

CLEAR Regulations should be coherent, logical, and practical. There should be a clear nexus between regulations and agency goals and objectives whether explicitly or implicitly stated. Agency positions should be readily understood and easily applied.

RELIABLE Regulations should be based on the best available knowledge from research and operational experience. Systems interactions, technological uncertainties, and the diversity of licensees and regulatory activities must all be taken into account so that risks are maintained at an acceptably low level. Once established, regulation should be perceived to be reliable and not unjustifiably mna state of transition. Regulatory actions should always be fully consistent with written regulations and should be promptly, fairly, and decisively administered so as to lend stability to the nuclear operational and planning processes.

Integrity in our working relationships, practices and dlecisions Excellence both in our individu~ii and cbill-ctive- a-ction-s Service to the public, and others who are affected by our work Respect for individuals' roles, diversity , and viewpoints Cooperation in the planning, management, and work of the agency' Commitment to protecting the public health and safety Openness in communications and decision-making Mission The mission of the U.S. Nuclear Regulatory Commission is to ensure adequate protection of the public health and safety, the common defense and security, and the environment in the use of nuclear materials in the United States.

NRC ORGANIZATIONAL VALUES