ML20134L291

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Rev 0 to UFSAR Rev Grpi
ML20134L291
Person / Time
Site: Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date: 01/08/1997
From: Haseltine J, Sarver S
CONNECTICUT YANKEE ATOMIC POWER CO.
To:
Shared Package
ML20134L236 List:
References
NUDOCS 9702180400
Download: ML20134L291 (7)
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CONNECTICUT YANKEE DECOMMISSIONING UFSAR REVISION GRPI Revision 0 January 8,1997 Prepared by'2 O jem Date / I E2 (S. (Sarver - UFSAR Lead Engineer) l Approved by  ! Date N9

. d. Hastltine - Design Engineering)

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CY DECOMMISSIONING UFSAR Revision GRPI  ;

Rev.0 Page 1 of 4 Goals:

l The goal of this GRPI is to provide those associated with the decommissioning of j Connecticut Yankee (CY) the necessary guidance to produce a revised l Connecticut Yankee (CY) UFSAR that accurately reflects the Licensing Bases and Design Bases (LB/DB) of those Structures, Systems and Components  :

(SSCs) necessary to support the plant as it evolves from cessation of operations I to a spent fuel storage facility. The UFSAR will also contain the Regulatory l Requirements and Programs necessary to support the evolution. The UFSAR  !

will 'oe revised to desc-ibe the as-built condition of the plant as it evolves from l cessation of operations to a spent fuel storage facility.  !

Roles': l The following states the role of selected groups and individuals associated with  !

the decommissioning of CY.

CY Design Engineering - Overall responsibility for oversight of UFSAR  ;

Revisions. i

- Determine the applicable Regulatory Requirements '

associated with the plant as it evoives from cessation  ;

of operations to a spent fuel storage facility.

CMP Licensing and -

Manage the ongoing UFSAR Revision development. l Administrative t

CMP UFSAR Group -

Coordinate the ongoing UFSAR Revision  :

Lead development.

CMP Licensing -

Identify the licensing commitments applicable to the Commitment Lead plant as it evolves from cessation of operations to a spent fuel storage facility.

CMP Design Group -

Determine the SSCs and Programs applicable to the plant as it evolves from cessation of operations to a spent fuel storage facility.

Develop the LB/DB of the spent fuel storage facility.

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] CY DECOMMISSIONING UFSAR Revision GRPl

Rev.0 1 Page 2 of 4 Process:

The following steps are those considered necessary to define the content of a

revised CY UFSAR that represents the plant as it evolves from cessation of 1 operation to a spent fuel storage facility.

. Accident Analysis

Define and analyze the accidents associated with the plant as it evolves from
cessation of operation to a spent fuel storage facility. These accidents will define the Technical Specifications, SSCs, Programs and any Regulatory l l Requirements that must be retained.  !

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e Finalize the design of a spent fuel storage facility l It is not necessary that this activity be completed prior to the issuance of the

. next revision to the UFSAR. It is however, necessary that the UFSAR  !

i accurately reflects the design when completed.  !

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e Regulatory Requirements j identify the Regulatory Requirements required for the plant as it evolves from  ;

i cessation of operation to a spent fuel storage facility. Regulatory l requirements include General Design Criteria (GDCs), NUREGs,10CFR,  !

etc., and possibly environmental regulations. l 4 i

. Revise the UFSAR l The revised UFSAR will contain information on SSCs and Programs that fit i into one of the categories described below. The UFSAR contents for each  ;

category will be substantially different, depending upon the applicable  !

category. To justify the revised sections, it is necessary that the 10CFR50.59s be evaluated and written to cover activities from cessation of l operation to removal of the equipment or termination of the program. The l

,- UFSAR will be revised to specify the abandonment or removal of SSCs, or termination of a program, when the action occurs.  !

1. SSCs and Programs required for a spent fuel storage facility.  !

, The UFSAR contents for this category will consist of normal UFSAR type information where the LB/DB is described in detail. These UFSAR sections are subject to change as the design is nMified. l l

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CY DECOMMISSIONING UFSAR Revision GRPI Rev.O Page 3 of 4

2. SSCs and Programs required for the decontamination / decommissioning process.

The UFSAR contents for this category will c,nsist of information that describes the function of the SSCs or Programs required during the decontamination and decommissioning process. These sections will briefly discuss why the original operating functions are no longer required and what function will be performed during the decontamination and/or decommissioning process. The applicable UFSAR sections will state that when a particular decontamination or decommissioning function has been completed, the SSC can be abandoned and removed, or that the program can be terminated, whichever is applicable.

3. SSCs and Programs not required at all.

The UFSAR sections for this category will consist of a discussion of why the SSCs or Programs are not required for the decontamination or the decommissioning process or to support a spent fuel storage facility. These sections will briefly discuss why the original operating function is no longer required. The applicable UFSAR sections will state that the SSC can be )

abandoned and removed or that the Program can be terminated,

. whichever is applicable.

. Necessary Procedure Changes in order to comply with the actions described in this document, and render the actions specific to CY, Nuclear Group Procedure NGP 4.03, " Changes  :

and Updates to Final Safety Analysis Reports for Operating Nuclear Power l Plans", will be changed by removing CY from the applicability. The NGP will be replaced with a CY specific Administrative Control Procedure (ACP).

Interpersonal Relations:

The following interpersonal relationship guidelines will be used to improve efficiency of the project and prevent duplication of effoits.

. The teams or groups should establish and maintain a liaison with Yankee personnel who have worked on similar areas for the Rowe decommissioning.

Efforts should be taken to learn from Yankee's experience.

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, CY DECOMMISSIONING l UFSAR Revision GRPI  :

i Rev.O j j Page 4 of 4 l 1 i t

. Members of a team or group should maintain open lines of communication. l Periodic meetings and self assessments within a team or group is strongly i

recommended. These meetings will result in feedback on progress and . l 1 pitfalls. I e Since several activities contain some degree of overlap, the group leads are .

. encouraged to maintain open lines of communication so that activities  !

] between groups is not duplicated.

. I g . To ensure that the revised UFSAR is accurate and internally consistent, an i Owner and Reviewer Matrix should be developed and issued. The matrix teill  ;

assign a single Owner to a particular UFSAR section. The Owner is ultimately responsible for the assigned section's accuracy. Several f

. i Reviewers may be assigned to a particular UFSAR section to assure overall l consistency.

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l . To assure that all necessary interfaces are established and required  ;

information is properly exchanged, an interface Matrix should be developed l

, and issued. The matrix will delineate wha' 'oput and output is required to be

exchanged between groups. f UFSAR Revision input  !

l The following input to the UFSAR Group is required to revise the C r UFSAR '

4' to describe the plant as it evolves from cessation of operation to a spent fuel )

. storage facility. l

. 1. SSCs and Programs that are not required at all.

2. SSCs and Programs that are required to support decontamination, including specification of the decontamination function to be performed.

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3. SSCs and Programs required to support a spent fuel storage facility.
4. LB/DB for a spent fuel storage facility.
5. Identification of applicable Licensing commitments, Regulatory Requirements,. Technical Specification changes, UIRs and ACRs.
6. 10CFR50.59 Safety Evaluations to support all UFSAR changes.

Docket No. 50-213 B16187 1

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I Attachment 4  ;

Haddam Neck Plant  !

Configuration Management Project  ;

Schedule Of Activities  !

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February 6,1997 l

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03 C CONNECTICUT YANKEE DEFUELED PROJECT SCHEDULE gh az JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC Nk 1997 1997 $

1 ACCIDENT ANALYSIS k__________A Q.'$ m i

2 SF HEATUPIDECAY a8 a

3 c CALCULATIONS k _ _ _A 55 3 SYSTEMS g ------ g EVALUATION y9O '

4 CORRECTIVE ACTION k_________________________________A "a PROGRAM 3 Ur 5 MANAGEMENT k_________________________________A y-STANDARDS s  ;

i 6 SYSTEMS '

RECLASSIFICATION k-----------------'----------A 7 DESIGN CONTROL g ------------------~~------------- g ,

PROCESS t

8 COMMITMENT MANAGEMENT g -----------------~~-----~~~------ g 9 LICENSING BASISI g'-------------------------- ------ g i DESIGN BASIS '

10 QA g ------------~~------------- g PROGRAM 11 SPENT FUEL POOL ISLAND STUDY g~------------------------------------ g ,

12 FIRE PROTECTION '

PROGRAM k-___________________________A 13 FIRE PROTECTION  !

TECH REQ MANUAL k____________________________A 14 UFSAR  ;

k______________________________________________A REVISION a

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