ML20198D637

for Comment Issue of Draft Reg guide,DG-1071, Std Format & Content for Post-Shutdown Decommissioning Activities Rept

ML20198D637
Person / Time
Issue date:	12/31/1997
From:	NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES)
To:
References
TASK-*****, TASK-DG-1071, TASK-RE REGGD-01.XXX, REGGD-1.XXX, NUDOCS 9801080239
Download: ML20198D637 (16)

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e# n\ g U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REGULATORY RESEARCH December 1997 Division 1 5 e Draft DG 1071

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/ s DRAFT REGULATORY GUIDE

Contact:

M, Masnik (301)4151191 DRAFT REGULATORY GUIDE DG-1071 STANDARD FORMAT AND CONTENT FOR POST-SHUTDOWN DECOMMISSIONING ACTIVITIES REPORT

[s&A A. INTRODUCTION m

k w Ih Decommissioning means permanently removing a nuclear fadflity'frorr'stwice and reducing hM)

R# M radioactive materials on the li.:ensed site to levels that would permit terrnination of the Nuclear Regulatory Commission (NRC) license. On uly 29,1996, a flhal fule Was published in the Federal 6' n M Register (61 FR 39278) amending the NRC's regulationIon the~ decommissioning procedures that will A gv g lead to termination of an opera,ing license for nuclear pcwer, reactors. This final rule included changes t

.v) to 10 CFR Parts 2, 50, and 51. (e ,t y

h The revised regulation,10 CFR 50.82(a)(dNI) requires that prior to or within two years e d following permanent cessation of operations, uthe licensee will provide the NRC wi;h a post shutdown m % A' decommissioning activities report SDA )?The PSDAR must include a description of the licensee's t

planned decommissioning activities lw. pscriedule for the accomplishment of significant milestones, and an estimate of expected costs. The PSDAR should also dncument the results of the licensee's evaluation of the enviroib$entalimpacts associated with site-specific decommissioning activities. The

%4 evaluation shouldfesulitro%mia comparison of the site-specifs environmentalimpacts of the proposed g%S %.

decomrnissioning witRthose impacts identified in previously issued environmental statements, the S V generic environ %mentailmpact statement (GEIS) on decommissioning (NUREG-0586, Ref.1) and the GEIS in s%g ~

upport of rulemaking on radiological criteria for license termination (NUREG 1496, Ref. 2). (

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Thes regulatory guide is being issued in draf t form to involve the pubhc in the earfy stages of the development of a regulatory position in this area.

It has not rece ved complete staff review and does not represent an official NRC staff position.

Pubhc comments are being solicited on the draf t guide (includmg any implementation schedule and its associated regulatory analysis or value/ impact statement. Comments should be eccomponied by appropriate supporting data. Writter comments may be submitted to the Rules

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er %rectives Branch, office of Administration, u.S. Nuclear Regulatory Commission, Washington, DC 20555-OC01. Copies of comments

) . ved may be examined at the NRC Public Document Room,2120 L Street NW., Washington, DC. Comments will be most helpfulif received

'v/ by March 31,1998. s .,,3 k;V U .

Requesta for single copies of active or deaft guidos (which may be repruduced) or for placement on an automatic distribution list for single copies of future draf t guides in specific divisione shou!d be made in writing to the u.s. Nuclear Regu' "-~mi=* ion. Washingto<t, DC 20555 0001, Attention: Printing, Graphics and oistribution Branch; or by f ax to (301)415-5272. I ljl[il ,

9801080239 971231  ;;

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PDR 01.XXX R REQGD PDR

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• The purpose of the PSDAR is to provide the NRC and the public with a general overview of the licenboa's proposed decommissioning activities. The PSDAR serves to inform the NRC staff of the licensee's expected activities and schedule, which facilitates planning for inspections and decisions regarding NRC oversight activities. Thu PSDAR is also a mechanism for informing the public of the proposed decommissioning activities before the decommissioning activities are conducted.

The purpose of this regulatory guide is to identify the type of information to be contained in the PSDAR and establish a standard format for the PSDAR that is acceptable to the NRC staff. The NRC staff suggests th.n licensees use this standard format to facilitate the preparation of PSDARs. This regulatory guide is being developed and issued in conjunction with Draf t Regulatory Guide DG 1067, " Decommissioning of Nuclear Power Reectors" (June 1997), also in support of the decommissioning rule (61 FR 39278).

Regulatory guidos are issued to describe and make available to the public such information as methcds acceptable to the NRC staff for implementing specific parts of the Commission's regulations, techniques used by the staff in evaluating specific problems or postulated accidents, and guidance to applicants. Standard format and content guides are developed to describe and delineate the information needed by the NRC staff in submittals from licensees. Regulatory guides are not substitutes for regulations, and compliance with regulatory guidos is not required. Regulatory guides are issued in draf t form for public comment to involve the public in the early stages of developing the regulatory positions.

Draf t repulatory guides have not received complete staff review and ou not represent official NRC staff positions, The information collections contained in this draft regulatory gu;de are covered by the requirements of 10 CFR Part 50, which were approved by the Office of Management and Budget, app.uval number 3150 0011. The NRC may not conduct or sponsor, and a person is not required to respond to, a collection of information unless it displays a currently valid OMB control number.

B. DISCUSSION Accordirg to 10 CFR 50.82(a)(S), the licensee is prohibited from performing any major decommissioning activities until 90 days af ter the NRC has received the licensee's r)SDAR submittal and until tts certifications of permanent cessation of operations and permanent removal of fuel from the reactor vessel have been submitted. Maior 2

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.- [ decommissioning activities are defined in 10 CFH 50.2 as ". . . any activity that results in

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permanent removal of major radioactive components, permanently modifies the structure of the containment, or results in dismantling components for shipment containing greater than u class C waste . . . ." Major radioactive components are defined in 10 CFR 50.2 as ". . . the -

reactor _ vessel and internals, steam generators, pressurizers, large bore reactor coolant system piping, and other large components that are radioactive to a comparable degree."

Upon receipt of the PSDAR, the NRC will docket the PSDAR and place a notice regarding its recolpt in the FederalRegister to solicit comments on the PSDAR fre i the public pursuant to 10 CFR 50.82(a)(4)(ii). A copy of the PSDAR will be made available to the public at the local public document room. The NRC will schedule a public meeting in the vicinity of the site to describe planned activities and to hear public comments. To the extent possible, the public meeting should be held within 90 days of the NRC's receipt of the s _ licensee's PSDAR submittal;it normally would be held about 30 days before the 90-day period ends.

The NRC wil! determine whether the licensee's PSDAR contains the information required by the regulation. Major decommissioning activities must not start until 90 days

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_ after the NRC receives the PSDAR. NRC review and approval of the PSDAR is not required; however, if the NRC determines during the review that the information provided by the licensas in the PSDAR does not comply with the requirements in 10 CFR 50.82(a)(4)(i). the

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NRC willinform the licensee in writing of the additionalinformation required by the regula-tions before 'he NRC staff holds the PSDAR public meeting and major decommissioning activities are b3 gun. A list of f actors that could cause the NRC io find the PSDAR deficient are given in Section 5 of this guide.

The above provisions for PSDARs apply to licensees who do not have an NRC-approved decommissioning plan by August 28,1996, which is the effective date of the final rule. - Decommissior'ng plans normally contain sufficient information to satisfy the requirements of the PSDAR. For licensees that have a decommissioning plan approved before August 28,1996, the approved decommissioning plan and the associated environmental review'are considered to be the PSDAR submittal (see 10 CFR 50.82).- If a

licensee had submitted a decommissioning plan before August 28,1996, and the NRC stafi

.c had not taken final action on the plan, the staff codders the decommissioning plan to be the PSDAR suomittal. l.icensees with an approved decommissioning plan are required to l'

i  : submit an update to the PSDAR for activities that were not considered in their docommis-( sioning plan. Because of the amount of material contained in the decommissioning plans I

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and the requirement to update this information, and because of the potential for a misunderstanding as to what must be updated, licensees are encouraged to. replace their decommissioning plans with a PSDAR cpdate that uses the format and content specified in this document.

C. FORMAT AND CONTENT OF THE POSTSHUTDOWN DECOMMISSIONING ACTIVITIES REPORT The purposes of the PSDAR are to (1) inform the public of the licensee's planned decommissioning activities, (2) assist in the schedifing of NRC resources necessary for the appropriate oversight activities, (3) ensure the licensee has considered the costs of the planned dacommissioning activities and considered the ft.nding for the decommissioning process, and (4) ensure the environmentalimpacts of the planned decommissioning activities are bounded by those considered in existing environmentalimpact statements.

The PSDAR submittal precedes any significant decommissioning activities as they are defined in 10 CFR 50.2. The tulo in 10 CFR 50.82(a)(4)(i) requires that the PSDAR include (1) a description of the licenste's planned mryor decommissioning activities, (2) a schedule for completing these activities, (3) an estimate of the expected decommissioning costs, and (4) a discussion that provides the reuons for concluding that the erovironmental impacts associated with site-specific decomunissioning activities will be bounded by appropriate pre-viously issued environmentalimpact statements. Each of these items is discussed in further detailin the following sections and the content expected by the NRC staff is described.

i. DESCRIPTION OF LICENSEE'S PLANNED DECOMMISSIONING ACTIVITIES The PSDAR should include a description of the licensee's planned activities for decommissioning. The purpose of the description is to info' the NRC and the public of the planned decommissioning bv p.oviding a general overview of the proposed decorrmissioning activities and identifying specifie activities to b3 accomplished or performed.

The licensee shoufd describe (in general terms) the method or combination of methods selected for decommissioning (i.e., long term storage followed by decontamination and dismantlemen: (SAFSTOR), or prompt decontamination and dismantlement (DECON), or partial decontamination and dismantlem6. t followed by long-term storage and then final decontamination and dismantlement). The licensee should also list and describe the major 4

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. activities and tasks related to decommissioning.: The activities and tasks'should be identified -

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• V and discussed briefly in the order in which they will occur. The level of detail of the descripe

' tion provided for each of the activities will depend, in part, on the nature of the activity, although normally it would be approximately a paragraph. Activities that are specific and unique to the f acility, and thus would require additional NRC staff oversight, should be described in greater detail than routine activides. For example, a chemical decontamination

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of a slightly radioactively contaminated system using a mild acid would only require a short -

description of the' process. However, it is expected that the use of a unique chemical decontamination method on a system containing large amounts of contamination (for instance, the primary system) would result in a more detailed description of the process for the staff to ascertain the level of oversight that would be requiied. Likewise, an activity that could result in an environmentalimpact that may be outside the bounds of those considered 11n the GEIS, such as the removal, processing, and storage of fuel debris contained in a system or in the spent fuel pool, would need to be discussed in greater detail, i For a prompt dismantlement (DECON),it is expected that activities such as the following would be described.

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• Removal of the reactor vessel crid internals

• Removal of other large components, including major radicactive components

. Removal of the balance of the primary system (charging system, boron control system, etc.)

+ General activities relating to the removal of other significant radioactive components and any structees .

+ Dernntamination of radioactive cornoonents, including the use of chemical decontamination techniques

-* Decontamination of structures or buildings, such as the au- ,. and fuel handling -

buildings

• - Special or unusual programs (for instance, removal and processing of fuel debris from the spent fuel rool) that might result in impacts that were not considered in the GEIS (these activities would need to be described in some detail)

+ . Onsite storage of components

. Shipment and prNessing of the low-levei radioactive waste, including any anticipated t  ; compaction or incineration of the waste-

+ Location of the ultimate disposal site for the low level radioactive waste 5~

e Storage or removal of the spent fusi and greater than-Class-C waste, including the ,

use (if planned) of an independent spent fuel storage installatic 1 (ISFSI) or wet storage f acility

+ Removal of hazardous radioactive (mixed) wastes.

• Changes in management end staffing, if long-term storage (longer than approximately 5 years) is selected as a decommis-sioning option, the activities relateo to preparing it,a f acility and site for storage should be listed and described. Activities and tasks for maintaining the facility and site in safe storage should also be mentioned. it is expected that the description of the preparation process and t'Te storage phase would specifically call out activities such as the following.

. Draining of specific systems and remnval of resins from ion exchangers

. Deccntamination of specific high-dose areas

. Removal of low-level waste that is ready to be shipped

. Shipment and processing or storage of the fuel and greater than-Class C waste

. De enargizing or deactivating specific systems

. Reconfiguration of ventilation systems and fire protection systems for use during the storage period

. Inspection and monitoring plans during the storage period

. Maintenance of any systems critical to final dismantlement during the storage period.

. Changes in management and staffing.

The activities relating to the transition from long-term Morage to decommissioning and activities relating to the final decommissioning of the facility should also be described to the extent known. According to 10 CFR 50.82(a)(3), decomr.lissioning will be completed within 60 years of permanent cessation of operation unless a longer term for completion is approved by the NRC as necessary for public health and safety.

These lists are provided merely as examples and are not meant to be allinclusive or to imply that a given licensee must include each of the activities in the decommissioning process. The description of the licensee's planned decommissioning activities is meant to be broad, but specific to the f acility; however, it should be complete and should include those activities occurring from the time of certification of permanent removal of the fuel to the anticipated termination of the license.

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(~} Details regarding the radiation protection plan, security plan, or discu sions on quality b assurance (OA) related to decommissioning are not required or expected in the PSDAR; how-ever, this information may be required in periodic updates to the Final Safety Analysis Report.

2. SCHEDULE OF PLANNED DECOMMISSIONING ACTIVITIES The purpose of the schedule is to >rovide information to the NRC and the public on the anticipated timing of decommissioning events, as well as to allow the NRC to schedule resources necessary for appropriate oversight activities. The temporal relationship between the activities should be shown for the major activities described in Section 1, so the reader undeistands the sequence of events as well as the timing of the events.

Schedules or diagrams should clearly indicate the estimated initiation and completion of specific tasks identified in Section 1. Any activities that will require a significant NRC licensing effort should be identified. including the start and desired end dates for activities such as the sulamittal of defueled technical specifications, the approval and licensing of an ISFSI, the licensing activities associated with a certificate of compliance for transportation of

'] major components, or the approval of the license termination plan. Changes to the schedule d following submittal of the PSDAR are addressed in Section 6, PSDAR Updates.

The level of detail of the schedule will depend on the timing of the activity and on the degree of oversight required by the NRC. The schedule for major activities in the near term should be given to the nearest month and year. Activities that will follow a storage period of at least 5 years may be schedu'ed to the closest year.

3. ESTIMATE OF EXPECTED DECOMMISSIONING COSTS The PSDAR should include an updated estimate of the expected decommissioning costs. The licensee will have already submitted a cost estimate for establishing a fund for decommissioning as required by 10 CFR 50.75(b). This estimate will have been revised periodically during operation. Licensees may alsc update their preliminary cost estimates required by 10 CFR 50.75(f)(1) and use the updated estimate in preparing the cost estimate required by 10 CFR 50.82(a)(4)(i). The updated cost estimate required by 10 CFR 50.82(a)(4)(i) may be (1) a site-specific cost estimate that is based on the activities and l schedule discussed in Sections 1 end 2 above, (2) an estimate based on actual costs at

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similar f acilities that have undergone similar decommissioning activities, or (3) a generic cost 7

estimate. The licensee's decision on which type of estimate to include in the PSDAR should be basad on specific plans for decommissioning, if a licensee has chosen extendedsafe storage of the f acility followed by decontamination and dismantlement, generic information would be acceptable to the NRC staff as cost estimates of final dismantlement could occur f ar in the future. The licensee is reminded that a site specific cost estimate is required within two years of permanently ceasing operation (10 CFR 50.82(a)(8)(iii)). The licensee should submit site-specific cost estimate data in the PSDAR if it is planning immediate decontamina-tion and dismantlement and is planning to spend more than 23 percent of the decommission-ing funds.

For generic cost estimates, see NUREG/CR-0672 (including Addenda 1 through 4),

" Technology, Safety and Costs of Decommissioning a Reference Boiling Water Reactor Power Station" (June 1980, Ref,3); NUREGiCR-0130, " Technology, Saf tty and Costs of Decommissioning a Reference Pressurized Water Reactor Power Station" (June 1978, Ref.

4); NUREG/CR 5884, " Revised Analysis of Decommissioning for the Reference Pressurized Wa:er Reactor Power Station" (November 1995, Ref. 5); NUREG/CR-6174, " Revised Analyses of Decommissioning for the Reference Boiling Water Reactor Power Station" (July 1996, Rof. 6); and NUREG-0586, " Final Generic Environmental Impact Staternent on Decommissioning of Nuclear Facilities" (August 1988, Ref.1).

The cost estimate could be a ccmbination of any of these or other methods. The cost estimates should be described briefly (e.g., site-specific, generic cost estimate, or one based or, similar f acihties). The costs should be described in relation to radiological decommission-ing (further broken down into subcategories such as large-component removal, planning, decontamination activities, low-level radioactive waste disposal, and decommissioning finance costs) for the appropriate level of detail for the cost estimate section. The submittal for this section could be as simple as a list, similar to the lists above, with the cost estimate for each task, a total cost estimate, and a description of how tne cost estimates were derived. Although cost data submitted as part of the PSDAR could be derived from a site-specific cost estimate, the level of detail required for the PSDAR estimate required by 10 CFR 50.82(a)(4)(i) is significently less than that required by 10 CFR 50.82(a)(8)(iii).

According to 10 CFR 50.75(b), the licensee must annually adjust the minimum amounts required by 10 CFR 50.75(c)(2) until the submission of the site-specific cost estimate that is required by 10 CFR 50.82(a)(8)(iii). If the licensee's PSDAR specifies delayed completion of decommissioning, the licensee must provide a means of adjusting cost estimates and associated funding levels over the duration of the storage or curveillance 8

_ period to ensure that '.5e appropriate amount of funding will be available to terminate the

() license [see 10 GFR 50.82(a)(8)(iv)). That mechanism should be described in the PSDAR. If the licensee has submitted a sita specific estimate as required by 10 CFR 50.82(a)(8Hiii), the means of adjusting the cost estimates should be described in the cost section of the PSDAR as well as in the site specific cost estimatJ.

4. ENVIRONMENTAL IMPACTS The PSDAR should include a discussion of the r9asons for concluding that the environmentalimpacts associated with site specific decommissioning activities will be bounded by previously issued environmentalimpact statements. The licensee should evaluate the potential environmentalimpacts associated with the site specific decommission-ing activities, including those activities listed in Section 1. The potential environmental impacts associated with decommissioning should be compared with similar impacts given in the Final Environmental Statement for the plant (as supplemented) and in the GEIS on decommissioning (NUREG-0586) (Ref.1) and radiological criteria for license termination; NUREG-1496 (Ref. 2). The comparison with impacts in the GEIS should recognize the unique (Q

'd nature of the site, if the postulated impacts associated with decommissioning have already been considered in the plant specific FES as supplemented, or the GEIS, the licensee should certify this in the PSDAR [see 10 CFR 50.82(a)(4)(ill. An analysis of the specific environ-mentalimpacts associated with decommissioning activities need not be included in the PSDAR. Support ing documentation and analyses must be available at the reactor site for inspection by the NRC staff, but do not need to be included in the PSDAR.

Potential impacts include both radiological an i nonradiological impacts. Examples of potentialimpacts that should be examined to ensure they are within the envelope of impacts .

predicted in the GEIS or FES include occupational dose; environmental releases to air, water, and soil and the resulting population doses; quantity of low-level radioactiva waste gener-ated; transportation impacts; and impacts from nonradiological hazards such as dust, noise, water use and hazardous (nonradiological) waste. Impacts to endangered and threatened species should be examined specifically. In many cases, the list of endangered or threatened species has changed since the most recent FES; a current list should be obtained from the appropriate U.S. Fish and Wildlife Service office. A determination should be made as to the

% I likelihood that a protected species is found on the site. If any species are likely to be d

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dffected by the decommissioning of the facility, this potential should be identified in the PSDAR. .

Any planned decornmissioning activity using a method not considered in the GEIS on decommissioning (NUREG 0586, Ref.1) could cause an environmentalimpact that has not becn considered and should be specifically examined. For example, the explosive destruction of ouildings that have not been decontaminated to levels that allowed their tree release would likely result in environmentalimpacts not considered in the GEIS or the site specific FES.

If s@lficant environmentalimpacts are identified that have not been considered in the plant specific FES or in the GEISs on decommissioning (Ref.1) and on radiological criteria for license termination (Ref. 2), the licensee is prohibited by 10 CFR 50.82(a)(6)(ii) from under-taking the activity that would result in such an impact without first complying with 10 CFR Part bl. The licensee rnust submit a supplement to its environmental report that relates to the additionalimr% cts under 10 CFR Psrt 51.

For plants that do not have ar; FES, an environmental assessment, such as that prepared for the cnange from a orovisional operating license to a full-ter T1 operating license, may be applicable.

5. FACTGRS THAT COULD CAUSE THE NRC TO FIND THE PSDAR DEFICIENT A number of iactors could cause the NRC to find the PSDAR deficient. These factors are directly related to the topics to be included in the centents of the PSDAR, as discussed above. The NRC could find the PSDAR deficient in the following circumsterices.

. The licensee's plan for decomr.iissioning could not be completed as described (for example. if the plan called for immediate decontamination and dismar.tlement of the f acility and there were no waste disposal f acilities available for the facility to use).

• The schedule included a decommissioning process that could not be completed within 60 years of the permanent cessation of operations as required by 10 CFR 50.82(a)(3),

unless it were shown that a longer decommissioning period is necessary to protect public health and safety (if so, approval would be made on a case-by-case. basis).

. The licensee's decommissioning plans, as presented in the PSDAR, included a decommissioning process thr, could not be completed for the estimated cost using the generic guidelines in the GEIS and using previous f acility decommissioning costs.

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. : _-.The PSDAR included activitics that would endanger the health'and safe't y of the public

by proposing activities that do not comply with the NRC's health and safety regula-

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tions or would result in a major detrimentall'mpact to the environment that is not bounded.by the current environmentalimpact statements.

6. S P_SDAR UPDATE.+

According to 10 CFR 50.82(a)(7), the licensee must notify the NRC, in writing with a copy to the affected States, before performing any sign!ficant decommissioning activity that_ i could be considered to be inconsistent with, or a significant schedular change to, the list of planned decommissioning activities or schedules described in the PSDAR. Changes that result in 'any type of ersvironmentalimpact not bounded by previously issued environmental impact staterrents would need a supplement to the Environmental Report. The supplement  ;

shuuld be submitted to the NRC, with a copy sent to tne affected States. Changes that I significantly increase the decommissioning costs also require notification to the NRC with a 2 copy sent to the affected States. -!

The PSDAR may be changed by the following process. Significant changes in major milestones, schedules, or the cost estimate require writter ';.tification to the NRC. Changes to the milestone schedule will be used by the NRC staff to schedule NRC inspections of the licensee's activities and to provide asserance that decornmissioning is being conducted safely l

and in accordance with regulatory requirements. Examples of changes in activities and schedule include, but are not limited to, cnanging from long term storage to active dismantle- l ment, changing the method used to remove the reactor vessel or steam generators from cutting and segmenting to intact removal, or changing the schedule to af fect major miles-toras. Examples of significant increases in cost associated with decommissioning the facility would include a new estimated cost greater than 20 percent above the site-specific cost estimate or the PSDAR cost estimate, or a 20 percent incr6ese in cost above a major milo-  !

stone estimate. The significant increase in cost would require written notification to the

- NRC; Changes regarding the removal _ of structures, systems, or components that do not

pose a direct or indirect potential rao!ological nazard need not be reported.

Changes in decommissioning activities should be evaluated as to their potential environmental hpact. If the expected impact is greater than that predicted in the GEIS or the site spe. ii FES,-or is outside the bounds of these documents, the licensee must notify -

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the NRC in writing and provide a supp.3 ment to the Environmental Report for the f at,ility that evaluates the impact of the change.

• For facilities that either have en approved decommissioning plan or have submitted a decommissioning plan before the effective date of the final rule, August 28,1996, the deco.nmissioning plan is considered to be the PSDAR submittal accordinC to 10 CFR 50.82.

This is consid6 red appropriate since the decommissioning plan was required to contain all the information required by the PSDAR, but in greater detail.

For facilities with approved decommissioning plans, decommissioning can proceed under the associated decommissioning order. Updates would be required, as specified sbove, if the information required in a PSDAR changes as described above. For f acilities that sub-mitted a decommissioning plan for aoproval prior to the issuance of the new rule but the NRC had not yet approved their plan, the 90-day period prior to initiation of major decommission-ing activities began August 28,1996.

Since the level of detail required in the PSDAR is significantly less than that required in decommissioning plans, licensees w%u Mve submitted a decommissioning plan for epproval or licensees with an approved deconfu aning plan are encouraged to extract the pertinent detail from the decommissioning p'an ind submit a PSDAR update in the format and content specified by this regulatory guide.

Written notifications to the NRC made under 10 CFR 50.82(a)(7) do not require a 90-day waiting period prior to initiation of activities. Typically, the staff would not require a public meeting to discuss the proposed changes. If, however, the licensee proposes changing the method of decommissioning, for example, from long term storage followed by decontamiantion and dismantlement to prompt decontamination and dismantlement, a public meeting would be held.

7. FORMAT OF PSDAR Graphic presentations such as drawings, maps, diagrams, sketches, and tables should be employed where the information may be presented more adequately or conveniently by such means. Due concern should be teken to ensure allinformation so fresented is legible, symbols are defined, and scales are not reduced to the extent that visual aids e'e necessary to interpret pertinent items of information. These graphic presentations should be located in the section where they are primarily addressed.

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jn7 References should appear either as footnotes to the page where they were discussed -

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or at the e'ad of each chapter.

Paper Size

- (1)- -Text pages: 81/2 x 11 inches.

(2) -- Drawings and graphics: 8-1/2 x 11 inchos; however, a larger size is acceptable i

provided the finished copy when folded does not exceed 81/2 x 11 inches.

1 Paper Stock and ink '

Use suitable quality in substance, paper color, and ink density for handling and reproduction'

-by microfilming or image-copying equipment.

. Page Map

- A margin of no less than 1 inch should be maintained on the top, bottom, and binding side of

- all pages submitted. -

- *3 Printing (1) . Composition: Text pages sF.ould be single spaced.

(2) Type Face and Style: Should be suitable for microfilming or image-copying equipment, including computer scanning.

(3) Reproduction: May be mechanically or photogrrphically reproduced. All pages of text should be printed on both sides and the image printed head to head.

Binding No requirements.

Page Numbering Pages should be numbered sequentially.

. Table of Contents A table of contents should be included.

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i Procedures for Updating or Revising P_ ages Data and text should be Jpdated or revised by replacing pages. The. changed or revised portion on each page should be highlighted by a " change indicator" mark consisting of a bold verticalline drawn in the margin opposite the binding margin. The line should be of

< the same length as the portion actually changed.

All pages submitted to update, revise, or add pages to the report should show the date of change and a change or amendment number. A guide page listing the pages to be inserted and the pages to be removed should accompany the revised pages. When major changes or additions are made, a revised table of contents should be provided.

Exceptions to Physical Specifications Other forms such as microform may be used; however, in accordance with 10 CFR 50.4(c), the licensco must contact the Division of Administrative Services, U.S. Nuclear Regulatory Commission, Washington, DC, 20555, telephone (301) 415-7166, to obtain specifications and copy requirements before making any submittalin other than paper form.

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REFERENCES (A) v

1. USNRC, " Final Generic EnvironmentalImpact Statement on Decommissioning of Nuclear Facilities," NUREG-0586 August 1988.

2. USNRC, " Generic Environmental impact Statement in Support of Rulemaking on Radiological Critoria for License Termination of NRC-Licensed Nuclear Facilities,"

NUREG 1496, Volume 1, July 1997.

3. H.D. Oak et al., " Technology, Safety and Costs of Decommissioning a Reference Boiling Water Reactor Power Station," NUREG/CR-0672 (Prepared for the U.S. NRC by Pacific Northwest Laboratory, Richland, Washington), June 1980 (Addendum 1, July 1983; Addendum 2, September 1984: Addendum 3, July 1988; Addendum 4, December 1990).

4. R.I. Smith, G.J. Konzek, and W.E. Kennedy, Jr., " Technology, Safety, and Costs of Decommissioning a Reference Pressurized Water Reactor Power Station," NUREG/CR-0130 (Prepared for the U.S. NRC by Pacific Northwest Laboratory, Richland, Washington), June 1978 (Addendum 1, July 1979; Addendum 2, July 1983; Addendon 3, September 1984: A '1endum 4, July 1988).

5. G.J. konzek et al., " Revised Analysis of Decommissioning fcr the Reference Pressurized Water Reactor Power Station," NUREG/CR-5884 (Prepared for the U.S.

NRC by Pacific Northwest Laboratory, Richland, Washingtoni, November 1995.

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6. R.I. Smith et al., " Revised Analyses of Decommissioning for the Reference Boiling Water Reactor Power Station," NUREG/CR-6174 (Prepared for the U.S. NRC by Pacific Northwest National Laboratory, Richland, Washington), July 1996.

7. U.S. NRC, " Report on Waste Burial Charges," NUREG-1307 Revision 4, June 1994.

NOTE: Copies of NUREG reports are available at current rates from the U.S. Government Printing Office, P,0. Box 37082, Washington, DC 20402-9328 (telephone (202)512-2249); or from the National Technical Information Service by writing NTIS at 5285 Port Royal Road, Springfield, VA 22161. Copies are available for inspection or copying for a fee from the NRC Public Document Room at 2120 L Street NW.,

Washington, DC; the PDR's mailing address is Mail Stop LL-6, Washington, DC 20555; telephone (202)634-3273; fax (202)634-3343.

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REGULATORY ANALYSIS l

A separate regulatory analysis was not prepared for this regulatory guide. The regulatory analysis prepared for the amendments to Parts 2,50, and 51, " Decommissioning of Nuclear Power Reactors," which was issued on July 29,1996 (61 FR 39278), provides the regulatory basis for this guide and examines the costs and benefits of the rule as implemented by the guide. A copy of this regulatory analysis is available for inspection or copying for a fee in the NRC Public Document Room,2120 L Street NW., Washington, DC:

the PDR's mailing address is Mail Stop LL-6, Washington, DC 20555: telephone (202)634-3273: f ax (2021634-3343.

UNITED STATES FIRST CLASS MAIL NUCLEAFI REGULATORY COMMISSION POSTAGE AND FEES PAID WASHINGTON. DC 20555 0001 PERM T N 047 OFFICIAL DuSlNESS PENALTY FOR PRNATE uSE. s300 120555064215 2 ISAISBlS111S US NRC-OIRM & RECORDS MGMT INFORMATION DOCUMENT CONTROL DESK LWFN-P117 DC 20555 WASHINGTON 0

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