ML20217N955
| ML20217N955 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 03/23/1998 |
| From: | Jorgensen B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Pederson C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| NUDOCS 9804090271 | |
| Download: ML20217N955 (27) | |
Text
. l M*4g ci, UNITED STATES NUCLEAR REGULATORY COMMlZION
./
/
801 WAR f L E ROAD o
,f USLE. ILLINOIS 60532 4351
- March 23, 1998 , ..h % h$f h .
MEMORANDUM TO hia D. Pederson, Director Division of Nuclear Materials Safety FROM: Bruce L. Jorgensen, Chief Decommissioning Branch
SUBJECT:
MEETING WITH COMED ON ZION STATUS AND PLANS On March 17,1998, John House and I met at the Opus Office of Commonwealth Edison with Messrs. Dick Tuetken, Manager, Decommissioning Projects; Ken Ainger, Licensing Manager; and Robert Godley, Manager, Zion Regulatory Assurance. The purpose of the meeting was to brir,g John, who will be the lead Division of Nuclear Materials Safety (DNMS) inspector for Zion, and myself up to date on current station decommissioning status and plans.
Short and long-term overviews were provided by licensee representatives. Public interest, reaction and involvement were discussed. Handling of " legacy" issues, including both plant l physical / radiological conditions and administrative issues (Oll's, enforcement, commitment tracking, etc.) were discussed.
The licensee provided a generic timeline (Attachment 1) for the next three years, broken down to monthly increments, showing projected staffing and selected major activities. Also included was ;
! a one-page, longer range (35 year) overview. Note from Attachment 1 the fact that the planned ]
staff reduction is la part a staff replacement. New personnel may constitute much of the i
" reduced" staff which will be on site by the end of 1998, because of changes in needed skills. ;
Note also that the transition to SAFESTOR will take until mid-2000, when the spent fuel island l conversion is completed and staff is finally reduced to about 40-50. A "SAFESTOR" condition ;
will obtain from about 2000 to about 2010, followed by about 10-12 years of " active l dismantlement." The current best estimate for fual shipment from the fuel pool (there are no plans for a dry cask storage project) is about the year 2015. /
In addition, one copy of a large package of information describing detailed plans and schedules was provided. John House will utilize the information as part of his inspection planning process, j in consultation with th6 resident inspector, to select optimal times for site visits. '
i l
A standardized collection of decommissioning plans has been developed by the licensee (Attachment 2) for use at Zion and other future decommiscioning projects. These were briefly discussed. The licensee also described their impressions of communityinterest in and potential public/ political issues which may arise. In sum, the local community is unhappy with the decision to decommission Zion, due to loss of jobs and tax revenue, and has expressed greater concem l about and resistance to the site as a " nuclear graveyard" than as an operating reactor. A local 9804090271 980323 PDR ADOCK 05000295 i P PDR I
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C. D. Pederson - " Advisory Council" of volunteers is in operation, and is conducting periodic meetings. An initial public meeting, at which the Council presents issues to Comed for review and response, was conducted on March 19 at the licensee's training building. It is expected that the Chairman of the Council may be the moderator for the NRC/ Comed public meeting when it occurs, perhaps on June 1,1998.
" Legacy" issues were discussed, and the licensee provided (Attachment 3) a description of their backlog evaluation process. The licensee's approach parallels that which the NRC is following,
- for items on the Open inspection items list.
John and I described the inspection approach being planned in DNMS, and indicated that tumover to our Division is likely before the public meeting. I provided a copy of the generic list of inspection procedures which may be utilized, in accomplishing the inspections specified in Manual Chapter 2561. Some issues which have developed at other decommissioning reactors were reviewed; the licensee personnel were knowledgeable of these issues.
It was agreed that a meeting should be held, about two weeks or so before the public meeting, at which time you and/or Roy Caniano can get a briefing about the latest status and plans and issues.
Attachmentsi As stated cc w/atts: R. Caniano, DNMS j cc w/o atts: K. O'Brien, DRP l
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Attachment 3 1
Zion S:ation comed l Zion Station Decommissioning Desktop Guideline i
l BACKLOGEVALUATIONPROCESS l
l l
REVISION 0 i
EFFECTIVE DATE l
DRAFT \
l Approval: Date:
Plant Decommissioning Manager
ATTACHMENT I EVALUATION CHECKLIST ITEM TRACKING IDENTIFIER:
ITEM DESCRIPTION:
l 1
l Part I Shutdown Plant Applicability Evaluation Checklist
{
1
- 1. Does the item apply exclusively to an SSC on the " Systems Not Required" list of Attachment 37 Yes The item need not be performed. Continue with step 6 No Continue with step 2 l 2. Is the item necessary to maintain the operability of an SSC required to be operable for a shutdown plant (use Attachment 2 to determine SSC applicability)?
l I
! Yes The item is necessary for continued plant operation and should be l performed. Continue with step 5 No Continue with step 3
, 3. Is the item necessary to maintain the functionality of an SSC required to be I
functional for a shutdown plant (use Attachment 2 to determine SSC applicability)?
Yes The item is necessary for continued plant operation and should be performed. Continue with step 5 No Continue with step 4 l
- 4. Is the item necessary to maintain the functionality of an SSC required to support the operation or maintenance of the Synchronous Condensers for Units 1 or 2 (use Attachment 2 to determine SSC applicability)?
Yes The item is necessary for continued plant operation and should be performed. Continue with step 5 No Continue with step 5
f ATTACHMENT I EVALUATION CHECKLIST i
- 5. Does the action involve Training or Tailgate activities for department (s) or individual (s) necessary to support activities associated with SSCs required to be operable or functional for a shutdown plant or to support operation of the Synchronous Condensers for Units 1 or 2 (use Attachment 2 to determine SSC applicability)?
Yes The item is necessary for continued plant operatien and should be performed. Continue with step 5 l
No Continue with step 6
- 6. Is the item an open NRC commitment?
Yes If closure or a change is desired, evaluate the item in accordance with Attachment 4 and provide it and this Evaluation to Regulatory Assurance Continue with step 7 No Continue with step 7
- 7. Is the item part of the Zion Recovery Plan?
Yes Provide a copy of the completed evaluation including attachments and supporting documentation (if necessary) to the Recovery Plan Manager No Continue with step 8
- 8. Is there any other reason why the item should remain open such as:
. Personnel safety concem (slip or fall hazards, electrical insulation degradation, plant lighting, confined space concerns, HVAC, or a housekeeping or sanitation issue)
. Hazardous material problem (leak integrity, contamination control, hazardous l material control, etc.)
l l . System lay up condition concern Yes The item should be completed
] No The item no longer needs to be performed i
ATTACilMENT I EVALUATION CHECKLIST l
l Part II Appropriateness of Closure / Suspension Checklist L
- 1. Does the issue involve an SSC required for a permanently shutdown plant (determined from Part I)?
Yes No
- 2. Does the issue involve a potential generic issue (e.g., chilling effect, nitrogen gas accumulation applicability to Byron or Braidwood, etc.)?
Yes i
No l l
- 3. Is the item subject to pending NRC enforcement or is involved in an ongoing NRC investigation?
Yes No
- 4. Does the item involve a willful violation of NRC requirements?
Yes
)
NO
- 5. Does the item involve a potential non-wit! Sal Severity Level III violation or !
higher (i.e., the control of safeguards material)?
i If All of the questions in Part II were answered 'No', complete the approval section, obtain Senior Manager approval, and close or suspend the item as appropriate.
If ANY question in Part II was answered 'Yes', review the item with the Site Vice President or j designee and obtain concurrence to close or suspend the item. Once concurrence has been L obtained, Regulatory Assurance must discuss the issue with the NRC before closure or suspension.
i
~7 T'"" ATTACHMENT I
.[,,, . EVALUATION CHECKLIST i-
[.
Par: N I?nal Approval l - (che:L s that apply)
At least one question in Part II was answered yes and Site Vice President (or
! designee) approval is required to close or suspend the item.
L l The' item has been satisfactorily addressed and it no longer needs to .be '
performed.
l^
l .
. The appropriate NRC commitment change documentation has been submitted to Regulatory Assurance and the Recovery Plan Manager as appropriate.
- - The item should remain OPEN and the appropriate tracking system has been venfied as OPEN.
l
(. Preparer Date ,
l Senior Manager Date The item has been discussed with the NRC (N/A if not required) j l
l Regulatory Assurance Date p
Site Vice President (or designee) Date d
i !
i I
r ATTACHMENT 2 OPERABILITY AND FUNCTIONALITY EVALUATION CHECKLIST System: System Name (SN)
Part I Operable SSC Checklist:
- CRITERIA FOR SELECTION OF OPERABLE SSCs YES NO I Does the SSC directly ensure safe spent fuel storage (e.g. reactivity control, cooling, shielding, etc.)?
2 is the SSC required " OPERABLE" by the Plant Technical Specifications or l Administrative Technical Requirements?
3 Does the SSC suppon the operation of SSCs required for the safe storage of spent fuel?
4 is the SSC credited to prevent or mitigate the consequences of any design basis accident for the plant in the defueled mode?
5 is the SSC directly connected with a " OPERABLE" SSC and incapable of being isolated such that it may compromise the capability of the " OPERABLE" SSC?
6 is the SSC required to comply with a License Commitment that is applicable in the defueled mode?
If any of the answers from Pan I are "YES", the SSC should be classified as " OPERABLE". Part 11 may be completed if portions of the system will not be required to be " OPERABLE". If all of the answers are "NO", then complete Part 11.
Part II Functional SSC Checklist:
- CRITERIA FOR SELECTION OF FUNCTIONAL SSCs YES NO I Does the SSC support facility habitability such as HVAC, sewage treatment, housekeeping, or plant lighting?
2 Does the SSC support the synchronous condenser project?
3 is the SSC required to maintain site insurance commitments such fire protection?
4 is the SSC required to comply with miscellaneous agency code requirements such as underground storage tank requirements or EPA exhaust emissions?
5 Does the SSC provide necessary miscellaneous water supplies such as potable water and demin water?
6 Is the SSC required to support maintenance activities such as miscellaneous cranes, compressed gas systems, power requirements, or instrument and service air?
? Is the SSC required to support necessary radwaste / chemistry functions?
8 Is the SSC required to support lake discharge releases?
9 Does the SSC provide a necessary support function such as instrument and service air, leak integrity, freeze protection, or system layup?
10 is the SSC necessary to maintain personnel safety or OSHA requirements such as slip l or fall hazard protection, confined space monitoring, or electrical insulation degradation?
If any of the answers from Part 11 are "YES", the SSC should be classified as " FUNCTIONAL" f
I L
ATTACHMENT 3 SYNCHRONOUS CONDENSER AND NOT REQUIRED SYSTEMS LIST l
i List of systems required to support the Synchronous Condensers Service Water Hydrogen /CO2 L Seal Oil Turbine Oil Main Power Bus Duct l Bus Duct Cooling Stator Water Stator Water Cooling List of Systems no longer required to support Safe Spent Fuel Storage or the Synchronous Condensers
! BD SG Blowdown CD Condensate (The CST may need to remain functional)
CI Containment Isolation CR MG SWGR &Rx Trip Bk l CR Control Rods and Drives l CS Containment Spray DT Reactor Coolant Drain ES Extraction Steam l FS = W Turbine Supervisory FW Aux Feedwater FW Main Feedwater HD Heater Drain HM Misc Heater Drains HR Moisture Separator Reheaters j IC Incore Systems IW Isolation Seal Water LL Loose Parts Monitoring MS Main Steam NR NuclearInstrumentation NT Nitrogen (except for Weir Gate seals and Waste Gas Decay Tank nitrogen blanket) l OG OEGu l PP Penetration Pressurization l RC Reactor Coolant
! RH Residual Heat Removal RP Reactor Protection RV Reactor Containment Ventilation (portions for habitability will need to be functional)
RV Hydrogen Monitors SC Condensate Makeup SI Safety Injection SS Nuclear sampling TC Thermocouples (Rx)
TD Tendons VC Chemical and Volume Control (makeup blender and control / pumps will need to be functional)
L
i.
t ATTACHMENT 3 SYNCHRONOUS CONDENSER AND NOT REQUIRED SYSTEMS LIST
'WS Secondary Sampling (Aux Steam will be functional) l i.
l t
l l
! I I
l l.
i l
I I
l l i
l I
ATTACHMENT 4 COMMITMENT CHANGE FORM l
ORIGINAL COMMITMENT DESCPJPTION:
l l
l SOURCE DOCUMENT: NTS #:
! REVISED COMMITMENT DESCRIPTION:
l l
l SUMMARIZE JUSTIFICATION FOR CHANGE:
l l
l l NOTE Refer to Attachment 2 for Guidance in responding to the following questions.
l I
- 1. Is a codified commitment revision process applicable and completed (i.e.,
l NO Continue with Step 2 YES EXIT PROCESS
- Use codified process.
l l
l i
I 1
ATTACHMENT 4 COMMITMENT CHANGE FORM
- 2. Could the change negatively impact the ability of a System, Structure, or l Component (SSC) to perform its safety function or negatively impact the ability of personnel to ensure the SSC is capable of performing its intended safety function?
NO Briefly describe rationale (attach additional sheets as necessary)
Continue with Step 3.
YES Perform a safety evaluation using 10CFR50.92 criteria and attach a copy. Does a significant hazards consideration exist?
YES EXIT PROCESS
- Do aqt proceed with the revision ! !
Discuss change with Regulatory Assurance. If the change is necessary, l
obtain approvals from NRC prior to implementation of the change.
NO Continue with Step 3 l l
- 3. Was the original commitment necessary for compliance with an obligation (i.e.,
rule, regulation, order, or license condition)?
NO Continue with Step 4 UYES Does the revised commitment preserve compliance?
1 NO EXIT PROCESS
- l Do pA proceed with revision !
Discuss change with Regulatory Assurance. If the change is necessary, obtain approvals from NRC prior to implementation of the change.
l l
i ATTACHMENT 4 COMMITMENT CHANGE FORM YES Briefly describe rational (attach additional sheets as necessary) 1 Has the original commitment been implemented?
NO EXIT PROCESS
- Provide timely notification of revised commitment to the NRC.
YES EXIT PROCESS
- l Notify NRC of revised commitment in next - Annual Commitment Change Summary Report.
l 4. Was the original commitment (1) explicitly credited as the basis for a safety decision in an NRC SER, (2) made in response to an 14RC Bulletin or Generic l Letter, (3) made in response to a request for information under 10CFR50.54(f) or 10CFR2.204, or (4) identified as long term corrective action in response to a NRC Notice of Violation?
I
! NO Continue with Step 5 YES Has the commitment been implemented?
NO EXIT PROCESS
- Provide timely notification of revised commitment to NRC.
l l YES EXIT PROCESS
- Notify NRC of revised commitment in next Annual Commitment Change Summary Report.
l
ATTACHMENT 4 COMMITMENT CHANGE FORM l
- 5. Was the original commitment made to minimize recurrence of an adverse condition f (i.e., a long-term correction action stated in a LER):
)
NO Change commitment No NRC notification required l YES Is the revised commitment necessary to minimize recurrence of the adverse condition?
[NO Change commitment No NRC notification required Briefly describe rationale (attach additional sheets as necessary) l I
l YES Notify NRC cf revised commitment in the next Annual j Commitment Change Summary Report.
- EXIT PROCESS means the balance of the evaluation is not to be completed. Proceed to !
the Commitment Change Evaluation Results section.
l 1
i t
ATTACHMENT 4 COMMITMEN't CHANGE FORM L
COMMITMENT CHANGE EVALUATION RESULTS Commitment change to be pur. sued:
Codified change documentation attached l
10 CFR 50.92 No Significant Hazards Consideration attached Timely notification of NRC required /NTS to revise commitment submittal attached Notification in next Annual Commitment Change Summary Report Required No NRC notification requi ed Commitment change cannot be made without prior NRC review and approval Commitment change not to M pun;ued PREPARER: DATE:
3 RESPONSIBLE MANAGER: DATE:
REGULATORY ASSURANCE SPECIALIST: DATE:
FOLLOWUP NTS ITEM NUMBERS:
REGULATORY ASSURANCE )
MANAGER: DATE:
)
l l
l .
ATTACHMENT 5 COMMITMENT EVALUATION GUIDELINE 4
NOTE.
Due to the sensitivity ofsome issues, it may be advisable to notify the NRC prior to making changes to Regulatory Commitments even though the following change process would not require such action.
- 1. IS THERE A CODIFIED CHANGE PROCESS FOR THE COMMITMENT?
NOTE The purpose of this guideline is to evaluate individual changes to regulatory commitments embodied in the UFSAR and not tojustify significant reductions in scope of a UFSAR.
l .
l Commitments that are embodied in the Updated Final Safety Analysis Report (UFSAR) as descriptions of the facility or procedures are changed by' applying the pmvisions of 10CFR50.59 to determine if an unreviewed safety question (USQ) j exists. If a complete 10CFR50.59 review determines that an USQ does not exist, licensees may make the change and provide a description of the change to the NRC l annually or coincident with filing UFSAR updates. Otherwise, prior NRC review l and' approval of the change is required. Regulatory commitments screened from complete application of the 10CFR50.59 criteria need not be further evaluated for their safety significance under Step 1 and should proceed to Step 2.
! Commitments that are contained in certain programs and plans required by j I
l 10CFR50.54 are changed by applying the provisions of the applicable section of l 10CFR50.54 (50.54(a) for Quality Assurance Plan, 50.54(p) for Safeguards l Contingency Plan or 50.54(q) for Emergency Plan). Changes that do not " reduce commitments" in the Quality Assurance Plan or that do not " reduce the l effectiveness" of the Safeguards Contingency Plan or Emergency Plan may be made without prior 11RC review and approval with notification of the change as specified in the applicable 50.54 section. Otherwise, prior NRC review and approval of the change is required.
I 2. IS THE CHANGE SIGNIFICANT TO SAFETY? ]
l Commitment changes that are not captured by the codified processes identified in i Step 1-~ still need to be evaluated in terms of their safety significance unless application of the 10 CFR 50.59 evaluation criteria under Step 1 determined that the change does not create an Unreviewed Safety Question.
L I i
a 4 ATTACHMENT 5 COMMITMENT EVALUATION GUIDELINE s The first step is to evaluate if the change could negatively impact the ability of a SSC to perform.its intended safety function. Relevant information in performing this evaluation is an understanding of the safety basis for the original commitment.
- A review of pertinent documentation (e.g., NRC Bulletin or Generic Letter, LER, NOV, etc.) that prompted the original commitment is a source for basis information.
! A further factor to be considered in performing the evaluation is whether the change could negatively impact the ability of licensee personnel to ensure the SSC is l capable of performing its intended safety function as a result of changes to l procedures, programs, and other human performance elements. If the evaluation determines that the change could not negatively impact the ability of a SSC to perform its intended safety function, the change is not safety significant.
If the evaluation determines that the change could impact the ability of a SSC to perform its intended safety function, then an assessment applying the criteria of 10CFR50.92 (c), (1) through (3), should be performed to determine if the change i
involves a significant hazards consideration. Probabilistic Safety Assessment (PSA) insights can be used to supplement deterministic-based assessments. If the assessment determines that a significant hazards consideration exists, the change is l significant to safety. Otherwise, the change is not safety significant.
l
- l. Changes to commitments that are evaluated as being significant to safety.would l~ either not be implemented or would require discussion with the NRC and review and approval, as appropriate. Changes evaluated as not significant to safety would )
proceed to Step 3 to assess if a compliance issue exists. !
- 3. WAS THE ORIGINAL COMMITMENT NECESSARY TO ACHIEVE COMPLIANCE WITH AN OBLIGATION? i Non-compliances with obligations are identified to licensees through notices of violation (NOVS) and non-cited violations. Responses to NOVs and some LERs include the immediate corrective actions taken to restore compliance with the ,
l l obligation. Additionally, licensees may have made specific commitments related to L the method of complying with obligations. Changes to these commitments need.to l l be evaluated to determine if the change would still preserve compliance with the obligation.
l If the change to the commitment would not preserve compliance, licensees would have the option of. not proceeding with the change, or applying for the appropriate ,
form of regulatory relief (e.g., exemption, license amendment, or order revision).
If the change to the commitment preserves compliance but the original commitment . '
has yet to be implemented, the licensee can proceed with the change. The NRC
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ATTACHMENT 5 i COMMITMENT EVALUATION GUIDELINE ._.
should be notified of the change as soon as practicable after the change is approved by licensee management but before any committed completion date. This should be done within 30 days provided the committed date is not sooner. Notification should l be accomplished by supplementing the docketed correspondence cor.taining the original commitment.
If the change to the commitment preserves compliance and the original commitment has been implemented, or is of a recurring nature, the licensee can make the change and provide annual or refueling outage interval notification to the NRC.
- 4. DID THE NRC RELY UPON THE ORIGINAL COMMITMENT BEING CONSIDERED FOR CHANGE)
Some commitments are made in response to a subject of regulatory interest where the NRC either reviewed and approved the action volunteered or agreed to by the licensee or relied upon the commitment in lieu of taking other action, such as issuing orders. Items in this category include: (1) specific statements in NRC Safety Evaluation Reports crediting specific licensee commitments as being the basis for an NRC staff safety conclusion (general references to an entire licensee report such as a Fire Hazards Analysis are not considered to be specific commitments in this context); (2) commitments made in response to NRC Bulletins ;
and Generic Letters; (3) commitments made in response to requests for information under 10CFR50.54(f),10CFR2.204, or Confirmatory Action Letters (CAL); and (4) commitments identified as long term corrective actions in response to a NRC Notice of Violation. Regulatory commitments may involve both new actions as well as existing actions credited by licensees in responding to NRC requests. For example, responses to an item in an NRC Bulletin crediting an existing program, practice, or plant feature as meeting the intent of the requested action is a regulatory commitment. Changes to regulatory commitments not captured in categories (1) through (4) would proceed to Step 5.
If the original commitment has yet to be implemented, the licensee can proceed with the change. The NRC should be notified of the change as soon as practicable l after the change is approved by licensee management but before any committed completion date. This should be done within 30 days provided the committed date l
! is not sooner. Notification should be accomplished by supplementing the docketed correspondence containing the original commitment.
l If the original commitment was made in response to a Notice of Violation, the licensee can proceed with the change but the NRC should be notified of the change as soon as practicable after the change is approved by licensee management if the I
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ATTACHMENT 5 COMMITMENT EVALUATION GUIDELINE l
commitment has been in place fewer than two years. Notification should be accomplished by supplementing the NOV response.
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For other commitments in this category, if the commitment has been implemented or is of a recuning nature, the licensee can make the change and provide annual or refueling outage interval notification to the NRC.
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- 5. WAS THE ORIGINAL COMMITMENT MADE TO MINIMIZE RECURRENCE .
OF AN ADVERSE CONDITION? I Commitments to take long-term corrective actions in Licensee Event Reports
! (LERs) are made to minimize recurrence of adverse conditions. A good measure of the effectiveness of these commitments is the success in avoiding recurrent adverse conditions. The NRC, under its enforcement policy, uses a two-year time period
- from the date of the last inspection or the period within the last two inspections, whichever is longer, as an indication' that the adverse condition related to a !
. particular area has been corrected.
Licensees may find it useful to periodically review the need for commitments
!. related to minimizing recurrence of adverse conditions. Licensees need the '
! flexibility to change or elim!.nate commitments they determine are no longer necessary based on:
- The committed corrective action may not have been successful in minimizing !
recurrence of the condition; or i l
- There may be a more effective way to minimize recurrence of the condition ,
other than the method selected; or i
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! - The commitment may no longer be necessary due to changing conditions at i the plant; or l
- In hindsight and based on experience, the commitment may never have been necessary to minimize the potential for future non-compliance. i
! --- The commitment may have subsequently been captured as part of an ongoing program or other administrative control that is subject to a revision review process (e.g., procedure changes govemed by administrative Technical Specifications).
If the changed commitment is necessary to minimize recurrence of an adverse ;
condition, the NRC should be notified of the change on an annual or refueling I
I ATTACHMENT 5 -
COMMITMENT EVALUATION GUIDELINE
, outage interval basis. -If the comrnitment is no longer considered necessary, the licensee may change the commitment without notifying the NRC.
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