ML20087A036

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Submits First in Series of Periodic Memo Appraising of Status of Accelerated Insp Program for Facility.Program Oriented Visits Listed
ML20087A036
Person / Time
Site: Oyster Creek
Issue date: 10/27/1967
From: Robert Carlson
US ATOMIC ENERGY COMMISSION (AEC)
To: Moseley N
US ATOMIC ENERGY COMMISSION (AEC)
Shared Package
ML20086U000 List: ... further results
References
FOIA-95-36 NUDOCS 9508040157
Download: ML20087A036 (8)


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c UNITED STATES GOVERNMENT Memorandum

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' To iN. C. Moseley, Acting Senior Reactor DATE: October 27, 1967 Inspector Re ion ~ I, Division of Compliance

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. T.. Ca son, Reactor Inspector j

Region I, Division of Compliance sUBJEcr: JERSEY CENTRAL POWER & LIGHT COMPANY LICENSE NO.

CPPR-15 COMPLIANCE INSPECTION PROGRAM STATUS MEMORANDUM NO. 1 I

This is the first in a series of periodic memoranda to keep you appraised of the status of our accelerated in-i spection program for the subject facility.

Only items of significance, including specifically problem areas -

actual or potential, will be highlighted.

The information i

presented this way will also be incorporated into formal inspection reports.

A.

Program Oriented Visits Dates' Place Visitors 10/10 JC Management Offices, Parsippany, NJ

Moseley, Carlson 10/12 Site Carlson 10/13 DRL-JC Meeting, HQ Carlson l

10/18 Site

Nolan,

& 19 Carlson I

10/19 f

& 20 Site Reinmuth Ii U

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10/20 ACRS Subcommittee Meeting, H St.

Carlson Fv::

10/25

& 26 Site Reinmuth 10/27 Site

Carlson, Gilbert.

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General Observations i

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e JC-GE""are attempting'to ready the facility to start initial core loading on December 29, 1967; This schedule is tight -

j and~ is based upon a limited completion approach.

Originally they were thinking in terms of readying a reasonably com '

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plete facility by the start of loading; however, they have J'

since reoriented their thinking and are now focusing on

.p' completing only. those portions considered by them to be l

I absolutely necessary for this purpose.

This change in thinking reflects recognition of two facts:

The signi-i ficant amount of work remaining to be done; and the i

time limitations as related to forecasted system power needs.

All of this ties in with the telegram from JC' f

to the Commission, dated October 13, 1967.

l Regarding the above, it is necessary from the Compliance viewpoint that JC get official acceptance (DRL approval by incorporation'in the operating license or by some other mechanism) of the work they propose to defer until i

after loading.

Incidentally, the current list of work i

to be deferred is substantially more than was discussed i

initially.

The JC-GE plans regarding official acceptance were pursued thru Mr. T. McCluskey, JC Plant Superintendent,

.l to both Mr. G. Ritter, JC Vice President,and Mr. R. Huggins, l

GE Principal Project Engineer, on October 25, 1967.

The j

answer received was that they had not planned any official submittal; however, they indicated that this would be l

looked into.

It is recommended that this issue be clari-1 fied with DRL at the earlient opportunity.

In the meantime, McCluskey understands that we plan

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to inspect on the basis of a complete facility while concurrently evaluating and formulating a position on j

1-some preliminary information we've been provided re-j lating to the proposed work to be deferred.

As can be seen in Attachment A, it would appear that GE has been quite liberal in deciding what is not required for loading.

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- A preliminary fix was obtained from GE regarding their J

broad schedule of events between'now.and turnover to j

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JC ' ~ This information is. sumanarized in paragraphic-f j

below.

Incidentally, it was quite. apparent from the t

difficulty experienced in eliciting this information f

j that GE's programming of the remaining phases of work.

l on this project is in a state of considerable-flux.

J Similar difficulties were experienced in obtaining hl other types of information as is discussed elsewhere in this memorandum.

One contributing factor may be 7

-the fact that a new man, Mr. D. K. Willett, Operations and Proj ect Completion Manager, is in the process of taking over for GE.

Mr. L. Koke, Resident Manager -

Construction, who has been present at the site for only a few months, is phasing out.

Willett reports to two different people, one of which

- i is Mr. R. Dickeman, Manager, Domestic Turnkey Projects.

i C.

Tentative Schedule of Events j

1 Time (Estima ted)

Events Present - 12/15 Complete preliminary pre-op testing.

12/15 - 12/22 Final pre-op testing.

12/22 - 12/29 Final reactor checkout and systems tests including integrated tests'.

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12/29 -

Start initial loading.

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12/29 - 20 to 30 Load; checkout. drives; initial startup days and low power tests.

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Note:

Reactor vessel head'and dry

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well head not installed.

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i Next 15 days Complete installation of core in-ternals (instrumentation); install heads (reactor and dry well); hydro.

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Complete all deferred construction work and tests.

Would not operate above some specified minimum power until complete.

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=Next 60 days Power ascension test program.

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Next 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> Full power demonstration run.

Turnover-to JC.

i Sununing up in the General area, from observations 'made' f

at' the site.to date, it would appear that their' goal of fy~

readying the facility for loading by December 29.is optimistic at.best, even granting deferrence of all-t that they propose.

1 D.

Problem Areas

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1.

Appearances at the job site reflect a general _ attitude of sloppiness.

This, combined with the pressures and i

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haste to complete the job within the limited time allotted and the continual last minute changes both l

in design and schedules, gives rise to question by us as to the quality of the finished product.

2.

Much information, needed for the compliance dfort, has-not been made available to us;as yet.

This includes j

the following:

a.

Lists of outstanding work and= schedules for completion.

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complete list of all tests and schedules for completion (attached list' of preoperat'ional-l tests is incomplete).

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Detailed initial loading and startup testing r

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program.

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Outstanding preoperational testing procedures h

3 (we have some).

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operating procedures - allfcategories;'i.e.,

a general plant, systems, instrumentation, j'

emergency, administrative, etc.

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Health physics manual.

3.

The assembly, ' including retrieval from the vendors, j

and filing of quality assurance records at the site

- is not now, and apparently will not be for some weeks, in a state of readiness sufficient for meaningful

. i compliance review.-

4.

JC's official review (sign-off) of-the : preoperational -

test procedures, being generated by GE, has been minimal thus far.

It'is noted that'there is an apparent reluctance on the'part of JC to. pursue this with any real vigor.

The stated reason has been that their most qualified manpower has been. tied' l

up on other matters.

Other conversational implica-l tions relate the reluctance to what this action might commit JC to in terms'of the contract.

This'latter point brings to question the whole area of JC qualifications.

5.

JC participation in this project, specifically that work going on at the site, appears to leave much to be desired.

Almost always when the subject is broached-with them, the answer relates their position' to the j

i nature of a turnkey job. - One wonders how much of a a

pig-in-a-poke package they are buying or, more u

specifically, how knowledgeable will they be,of the A

as-built. facility at the time of turnover..

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x 6-67 During tho~ December 18 - 20, 1967 visits, the reactor.

44 pressure vessel wa.s observed to be_ open and. full'of 4

.. greasy-looking water.- (post-plant ' systems flush - stage)'.

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l' No. covering to prevent entrance of foreign objects.

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was;provided.. Subsequent discussions with JC and GB; l

f.,y-during which the Fermi experience 'was discussed, in-dicated that they were not concerned here because the system flushing wattarranged, specifically with f'

i the reactor vessel serving as the sump.

They stated i

that the. vessel would be given a. final cleaning and i

p detailed inspectist prior.to-loading..They'also agreed.

j that a covering was nevertheless in order and said that one had sinco been installed.

7.

A control rod drive housing leak detected during the l

primary system hydrostatic test is unresolved; however, 1

this problem is being pursued by JC and GB..

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. 8.

Welds on portions of the emergency core cooling piping, previously not radiographed, have since been radio-graphed with a~ reported " substantial" rejection rate.

Repairs are currently under way.

We plan to continue a close examination of this area.

A request for authorization to use - our consultants,. Parameters, Inc.,

in the examination of welds on this and other systems, including the recirculation system, has already beon submitted to you.

9.

A preliminary review o,f the information which has.been made available regarding the control rod drive isystem I

testing program indicates that'only a minimal program W

has been proposed.

Also, that any hot' testing.would be.

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deferred until nuclear heatup.

Our initial reaction

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is that.what they have proposed is inadequate; however,

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,f our final position.

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10. ~ Information received. thus far in the. area of hot i

j functional tests indicates that they'do not plan

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to generate any significant amount of steam before core loading.

Consequently, the major portions of any hot functional tests would be deferred until the time of nuclear heat.

This

~f area warrants immediate consideration by, Compliance.

6:

The above defined problem areas have.been discussed with the senior GE and JC personnel at the site.

Both parties were responsive to some degree.

Further discussions are planned.

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F. J. Nolan, CO:HQ G. W. Reinmuth, CO:HQ I

M. S. Hildreth, CO:I-R. G. Gilbert, CO:I i

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.Att'chment A...

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QUIRED FOR INITIA!.

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_ SUP.v.ARY OF PRE-OPERATIONAL TESTS.0EFINING FUEL LOA 0iNG IV

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ProCeduro TITLE _

L No.

Not Required i

Drywell and Absorption System

  • Partial

, A-1 Reactor Vesscl Components Not Required A-2 Safety and Relief Valves

  • Not Required i

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A-3 Primary System Expansion Required A-4' l

Control Rod Drivo Hydraulic System i

A-5

  • Required 4

Not Required Control Rod Drive l

A-6 Recirculation System and MG Sots Not Required Emergency Condenser Not Required A-7 A-3 Reactor Shutdown Cooling Partial

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A-9 Reactor Cleanup System A-10 Required Partial Poison injection System Not Required -

A-11 Core Spray Containment Spray Not Required A-12 Not Required A-13 Containment inerting

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A-14 Fuel Pool Cooling A-15 Partial.

Fuel Handling Equipment NotRecfuired A-16 Reactor Head Cooling j

Not Required s

A-17

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,t Not acquired Turbine Oil System Turbine Control & TG Instrumentation Not Required

' B-1 Stcom Cycle; Scal Reg., Gland Exhaust Not Required.

B-2 Cen. Cooling Not Required B-3 0-4 Main & Sparc Exciter Not Required' B-5 Condenser and Auxiliary Hotwell, Vacuum Not Required T C-1 Condensato and Feedwater Not Required \\

C-2 Circulating Vater System Required C-3 Service Water System Not Required C-4 Condensate Demineralizer System Required C -5 Hakeup and Domestic Water System Required C-6 Turbine Building Cooling Water Required C-7 Reactor Building Cooling Water Required i

C-G Instrument and Service Air System Not Required

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Required C-9 Fire Protection System C-10 Plt. Heatin'g loiter Partini Ventilation, Turbine, Reactor, Radwaste and C-Il Access Control Not Required C-12 Required Drywell Vent.

C-13 Standby Gas Trcciment System Partial Liquid Radwaste System Not Required C-M C-16 Solid Radwasta System C-17 4

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