ML19312C704

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Describes Addl Info Required for Review of FSAR Re Crew Size Emergency Plan,Industrial Security,Review & Audit Functions, & Initial Tests & Operation
ML19312C704
Person / Time
Site: Oconee  Duke Energy icon.png
Issue date: 09/26/1969
From: Mcgough J
US ATOMIC ENERGY COMMISSION (AEC)
To: Schwencer A
US ATOMIC ENERGY COMMISSION (AEC)
References
NUDOCS 7912190908
Download: ML19312C704 (4)


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G S ep temb e r 26, 1969 A. Schuencer, Project Leader, Reactor Projects Branch No. 3, Division of Reactor Licensing TIIRU : Dudicy Thonpson, Chief, Operational Safety Branch Division of Reactor Licensing REVIE..' 0F GCONEE LTJITS 1, 2, & 3 (DOCKET Noa\\. d 50-270, 50-269 AND 50-237)

Ue have nade our preliminary review of the FS/G as suiamitted by Duke Poter Cempany for their Oconee 1, 2, and 3 Statica.

In or-der to continue with our evaluation, we need additienal informatio.

in the areas of:

Crew Size, Emergency Plan, Indus trial Security, Revie & Audit Functions, and Initial Tests & Operation.

Further questlous will be dependent upon the respcase of the applicant.

Crei SL:-

The organizational chart indicates Duke Peuer proposes operation of Unita 1 and 2 f rom a comon control roct with 4 men /shif t.

As Unit 03 gces into operation, with a separate centrol room, the crew will be augrented by an additional 4.ca/shif t giving 8 men / shift for 3 units located at one site.

These s taf fing proposals contras t sharplf with the recommended creu sizes of 3 and 13 nen/ shift re-spectively, as set forth in OS3 Guide #11, Guide for Nuclear Power Plant Shift Staffing.

Since each unit in the comple:r vill be phased into service at ap-proximately yearly intervals, Unit #1 will operate singularly for th is initial time period.

Accordingly, our evaluc. tion of crew size vill be based on single, dual and triple unit cperation.

In order to proceed uith our evaluation additional information in the follouing areas ic needed.

What will the shif t size, composition, and license requirements be for Unit 01 op2 ration? Provide the details of the traasition

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b. Schwencer 2

to dual and triple unit operation.

Uhat procedural and adminis tra-tive controls will be utilized to prevent interference with the operating units as a new unit is phased into service?

Will any of the operating crew be qualified in llealth Physics?

We note that only three such technicians are indicated for triple plant operation.

Provide the justificatica for the adequacy of this grcup.

Organizational charts for single, dual, and triple unit operation should be prepared sheuing the disposition of their proposed operating cre".

In particular any cross licensing requirenants between units should be indicated.

It should also be pointed out to Duke Power that a suf ficient number of licensed senior operators should be present to direct the activities of each unit.

Their present organization dces not reflect such s taf fing.

Figure 12-4 indicates that the Assistant Plant Superintendent vill hold a Senior Operator's license; ho;:cver, the position description and minimum qualifications indicate otherwise.

This pointJ needs clarification.

The preposed shif t staffing for dual and triple unit operation is an arca of substantial concern.

Duhe Power should provide the basis for their determination that such a creu size can adequately respond to plant operating requirements during routine and en2rgency conditions.

We would suggest that an analyais be perforced far a variety of expected plant conditicas, using time and motion techniques, to demonstrate that nanpo*:er requirenents are suf ficient.

Emergency Plan Information describing Duhe Pcwcr Company's plans for dealing with crergencies is referenced and an outline submitted; ho. ever, it is insufficient for evaluation.

Conscquently, the applicant should s ubnit their Emergency Plan including:

the basis and objectives; the caergency organization including assignnants of authority and responsibility; identification of c:argency conditions conqidered; designation of protective measures to be taken tihen specific prede-termined action levels are* reached; technical bases for the plan; adequacy of emergency centunication netuori:s ; no tification responsi-bility and authority of of fsita agencies and cupport groups, in-cluding medical arrangements; training requirenents ; and provision for revicw and updating.

Information presented sheuld be in sufficient depth and detail to pernit an evaluaticn in terma of protection of the health and safety of the public.

A. Schuencer 3

Industrial Security Information describing the extent of perimater fences, security lighting, guards, control room access, visitor accountability, and other site surveillance methods should be presented.

In addition, an analysis should be made to determine that critical plant features are suitably protected from acts of simple sabotage.

Provisions to be taken to limit access of construction personnel and to prevent inadvertant operation of equipment during the construc-tion of Units 2 and 3 should be stated.

Review and Audit Section 12.5 in the Cenduct of Operations and Section 15.6.1 (F) of the proposed Technical Specifications were revieued.

For this stage of the licensing process, our comments are directed to the Technical Specification portion only.

Station Review Cocnittec:

Provision should be made for recording and forwarding minutes and recommendations of the ccetings to the Plant Superintendent and other higher members of management.

A statement of the measures to be taken to prevent degradation of the qualifications of the group over the service life of the f acility shculd be included.

General Office Review Committee:

The composition and quali-fications proposed for this committee are too vague.

The applicant should designate the Chairman and marbers by either position or area of technical specialty.

The collectiva ex-pertise of the total coamittee should enconpass as broad a selection of applicable technical areas as possible.

A specified meeting f requency should be s tated.

For a formal committee such as this, a minimum of quarterly is considered adequate.

A s tatement of the measures to be taken to prevent future degradation of the qualificaticns of the committee should also be included.

Initial Tests and Operation Describe the organizational structure and relationship betv2cn the applicant and vendor for each phase of operation from preoperaticnal through ccamarcial poner generation.

Include assign = cat of responsi-bilit/ and authority for conduct and approval of tests and procedures, evaluation of results, and resolution of system and equipnant anonolies.

i Indicate by positien and organization those personnel expected to possess operator licenses.

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Provide the objectives for those tests performed prior to fuel loading.

Include those design objectives which will be verified.

Supply a description of the pre-startup chechs listed in Section 13.2.2.

Include the initial conditions and a brief test outline.

For those tests in Table 13-2 which comprise the Posteriticality Test Program, provide the conditiens under which the test will be conducted and the acceptance criteria.

J. M. Mc Gough Operational Safety Branch Division of Reactor Licensino ec:

D. J. Skovholt C. G. Long

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