ML20134L238

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Rev 0 to Accident Analysis
ML20134L238
Person / Time
Site: Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date: 12/19/1996
From:
CONNECTICUT YANKEE ATOMIC POWER CO.
To:
Shared Package
ML20134L236 List:
References
NUDOCS 9702180375
Download: ML20134L238 (7)
v • d • e


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Docket No. 50-213 B16187

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l Attachment 3 Haddam Neck Plant Configuration Management Project i Description Of Activities i

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.j February 6,1997 i

9702190375 970206 I l PDR ADOCK 05000213 '

P PDR }

Connecticut Yankee CMP Decommissioning l

ACCIDENT ANALYSIS i GRPI d

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Prepared by:

/ /ff/9[9(o Date J/

Approved by: ~ J.>' ' . M A

/ //_//r/pf Date Revision 0 4

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i Accident Andysis' )

GRPI Rev. O  ;

Page1 l i

Accident Analysis j GRPI l Goals:

l The goal of this effort is to revise the UFSAR for the accidents which are applicable to decommissioning activities and to the Spent Fuel Pool Island.

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j Roles:

The following groups, as shown in Table 1, will participate in the definition and

. calculation of the applicable accidents, and in the revision of the UFSAR.

The roles and responsibilities for personnel associated with the tasks are as followsi

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. The Director of Engineering will appoint one person to monitor all the accident j

! analysis tasks to completion. j

. The "P" Group department head will appoint a task leader and support personnel for each task.
j. . - The "P" task leader will be responsible for preparation, coordination, and issuance of i the task deliverable. 1

. The "R" Group department head will appoint a reviewer for the task.

. The reviewer of the task will be responsible for review and comment on the task deliverable, and for dispositioning all comments to the mutual acceptance of the task i leader and task reviewer.

i Process:

i The following steps are those considered necessary to produce the accident analyses which are applicable to decommissioning and the spent fuel island. -

1. Decommissioninn A.' Release of Surface Contamination

. Define the equipment which will be removed from the site

. Determine whether or not the equipment will be decontaminated

. Determine by health physics surveys the radioactive isotopes that are adhering to the surfaces of the equipment

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f Accident An11ysis l GRPI Rev. 0 Page 2 {

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< . Perform a calculation of the amount of radioactivity that, if released, would  ;

yield the maximum allowable site boundary dose, and the maximum allowable >

l worker dose.

. Prior to lifting the equipment with adhering radioactivity above the maximum ,

, limit, develop protective measures to reduce potential doses due to a drop accident (e.g., wrapping, enclosure with filtration, etc.)

B. Liauid Radwaste Failure l 1

. Determine the liquid radwaste and resin transfer systems that will be utilized.

l . Calculate site boundary dose due to the radioactive isotopes that may be l released due to a radwaste/ resin system failure. See Reference 1.

2. Sant FuelIsland 3
a. Defme the accidents which are applicable during operation of the spent fuel island. The accidents have been identified in Reference 1 and are in the following categories:

. Design Basis Accidents

. External Hazards

. Internal Hazards j . Anticipated Operational Occurrences  !

. Beyond Design Basis Accidents

b. Identify the safety related functions of systems, structures, and components j

. (SSCs). See Reference 2. .!

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c. Determine the regulatory requirements and commitments made with respect to i the accident mitigating features of the SSCs. See Reference 3. -l 4

- The tasks to be performed for each accident category are as follows:

. Design Basis Accidents  !

Prepare accident analyses for the design basis accidents, with and without taking credit for mitigating features. For radiological accident analyses, calculate worst case i

off-site and on-site doses.

Revise Section 15 of the UFSAR to address the design basis accidents.

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Accident Andysis GRPI Rev. O Page 3

. External Hazards Evaluate the capability of structures, systems, and components to withstand the  :

effects of external hazards.

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i Revise Sections 2 and 3 of the UFSAR to address the external hazards.

Internal Hazards Evaluate the capability of systems, structures, and components to withstand the effects of the internal hazards. An input required for this task is a list of the buildings, systems and components which will be operational to support the Spent Fuel Island.

This list is required to determine whether or not the effects of pipe whip, jet impingement and flooding due to pipe breaks need to be considered.

Revise Sections 3,9 and 10 of the UFSAR to address the internal hazards, as applicable.

. ' Anticioated Ooerational Occurrences Evaluate the capability of the Spent Fuel Island to withstand anticipated operational occurrences.

Revise the UFSAR to address these occurrences. The sections which will require a revision will most likely be the sections which describe the affected system (e.g.,

failure effects table).

. Beyond Desian Basis Accidents Evaluate the capability of the Spent Fuel Island to withstand accidents which are beyond the design basis, but which have been previously evaluated during the ,

operation of the plant. These accidents are considered part of severe accident I management such as Emergency Plan response, j The evaluations of these accidents will not be addressed in the UFSAR revision for j the Spent Fuel Island. j

f Accident Analysis GRPI Rev. O Page 4 Interpersonal Relations:

The following interpersonal relationship guideline should be used to improve efficiency of the project and prevent duplication of efforts.

. Personnel in the groups shown in the table in this GRPI will perform as indicated. ,

The preparers shall maintain an open line of communication with other groups who i have an interest, or who can provide expertise, in the task.

Interfaces with Other GRPIs: 1

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The accident analysis tasks as outlined in this GRPI can be accomplished successfully with the following inputs and outputs from/to other GRPIs.

Inouts Reauired From:

. Nuclear Island Design Specification GRPI (for identification of SSCs)

. Post-Shutdown Decommissioning Activitias Report (PSDAR) GRPI (for identification of decontamination source terms and liquid radwaste systems).

Outouts Submitted To:

. Emergency Plan GRPI (for radiological accident consequences and beyond design basis accidents)

UFSAR GRPI (for revisions to the UFSAR)

. Environmental Assessment (for revisions to Environmental Impact Statement)

References:

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1. DECY 96-1210, CY Definition of Accidents for Mode Defueled, dated December 4, 1966.  ;
2. DECY 96-1213, Definition of Safety Related Functions for Mode Defueled, dated December 17,1996.
3. DECY XX-XXXX, Applicability of the NRC General Design Criteria to Mode Defueled (later).

Accident Analysis GRPI Rev. 0 Page 5 Table 1 - Groups Responsible for Accident Analysis Tasks Group T Definition of Definition of Prepare Accident Prepare Accident Prepare Draft Revise A Accidents Accidents Related Analyses Analyses UFSAR UFSAR S Related to Spent Fuel (Radiological) (Thermal /Ilydraulic) Write-up K to Decomm/Decon Island Only Design P P R Radiation Assessment R R P P Safety Integration and Analysis R P P Systems Eng. R R R R R Operations R R R R R llealth Physics R R R R R Licensing R R R R R P P = Lead Group Responsible for Preparation and Approval of the Task R = Group Responsible for Review of the Task f-

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