ML20087A057
| ML20087A057 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 10/30/1967 |
| From: | Sears J US ATOMIC ENERGY COMMISSION (AEC) |
| To: | |
| Shared Package | |
| ML20086U000 | List:
|
| References | |
| FOIA-95-36 50-219-67-05, 50-219-67-5, NUDOCS 9508040164 | |
| Download: ML20087A057 (57) | |
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3 U. S. ATOMIC ENERGY COMMISSION REGION I
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DIVISION OF COMPLIANCE l
October 30, 1967 i
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CO REPORT NO. 219/67-5
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Title:
JERSEY CENTRAL POWER & LIGHT COMPANY k
LICENSE NO. CPPR-15
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Dates of visits:
September 22, 1967 and 4$
September 28 - 29, 1967
/77-r By Jo R. Sear, Reactor Inspector a
SUMMARY
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The plant status of construction for Oyster Creek is described.
Instrumentation and wiring and the completion of the radio-active waste building are principal items of equipment
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incompletion. The quality assurance system is discussed.
During the primary system hydro, a leak was found in a control rod thimble.
Operator training is up to date.
One key man,.the Technical Supervisor, is only at the site part time.
No gas or smoke detectors are planned for fire detection.
Health physics, operating, emergency, chemical, and maintenance procedures are being developed, but are not yet ready for review.
1o The preoperational test program is outlined, together with l
a list of items in the program requiring further study and I
a list of items whose completion GE wants to defer until after loading.
An interview was held with the Jersey Central Power & Light Company Vice President on organization and procedure.
i (continued) 9500040164 950227 PDR FOIA DEKOK95-36 PDR
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. Scope of Visits j
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p, Visits have been made to khe site o.f the: Jersey Central-.
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Power;& Light Company (JC) reactor at Oyster Creek, Now?
l Jersey, during :1967 by Mr. John'R. Searsi Reactor, Inspector, j
-Region I, Division of Compliance, on.the following' dates:
U February 23 - 24',EMarch 3 - 4, April 16-and 25, May.12, j
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July.18, 27. - 28, August 9,' and September 28
.29.IFormal j
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reports have been written for the February 23.- 24, March 3'- 4,7
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' April 16, and July 18 visits.,
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i The visits on April 25 and July 27 - 28 were in: conjunction
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with meetings at' the site.between the applicant and DRL-ACRS' consultants and subcommittees.
The' visits on May 12 andf August 9 were for the purpose of conducting tours of the-reactor for the following:
May 12 - Mr. Robert Engelken,
. Assistant Director for Reactors, Division of Compliance,
]
Headquarters, and Mr. George Spencer, Senior Reactor Inspector, Region V, Division of Compliance; and on 5
August 9 - Dr. W. Stratton, ACRS and Mr. John Rizzo,
' Division 'of Compliance, Headquarters. These visits we re.
j primarily familiarization. visits for the inspector.
Since.
j compliance information was not developed in depth, no formal -
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j reports were. written.
Information gathered during those, visits is included in this report.
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4 The inspector-has attended meetings in Bethesda between DRL, JC and GE on the following dated:
April 4 - 5, May. 4 - 5, May 17 - 18, June 22, August ' 3.- di and September 6 for the.
gF 'gy purpose of contributing information and of becoming familiar
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with the design and with DRL's hazards analysis. of the design.
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The inspector was accompanied on September 28 by Mr." Norman R
C. Moseley, Acting Senior Reactor Inspector, - Region I, Division I
of Compliance.
The visit on September 28 - 29 had originally
-l been scheduled for the second' week of' September and was. to be '
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-made in' time to witness the hydro test of the primary system.
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Labor disputes kept delaying the time of this test until September 29, when the test was witnessed by *the inspector.
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Scope of Visits (continued) -
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on September 22, the inspector had a conference on
- k organization and procedure with Mr.- George Ritter, Vice j
~8F President, JC, at the new offices of the General Public Utilities Corporation (GPU) Nuclear Power Grpup' in Parsippany, j
'New' Jersey..
a The visit on September 28 - 29 included tours of the
'i reactor, witnessing of the primary system hydro test, review of the preoperational test ' procedures, and discussions with the following:
General Electric Company f
i Mr. L. Koke, Project Manager
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Mr. A. Dunn'ing, Construction Manager 3
Mr. K. W. Hess, Operations Manager Mr. C. Lewis, Principal Plant Test Engineer -
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Mr. W. Bibb, Plant Test Engineer Mr. R. Green, Instrumentation Engineer Mr. E. Wester, Construction Electrical Engineer Mr. W. Royce, Expediting Engineer Jersey Central Mr. T. McCluskey, Plant Superintendent Mr. D. Hetrick, Operations Supervisor Mr. J. Roth, Shift Foreman Mr. R. Doyle, Chemical Supervisor Mr. N. Nelson,. Maintenance Supervisor j
Mr. D. Kaulback, Radiation Protection Supervisor Mr. C. Agon, Assistant Technical Engineer Mr. R. Sallivan, Assistant Technical Engineer 1
Mr. B. Cooper, Control Room Operator Mr. T. Morrison, Control Room Operator s-(continued) l I
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Results of Visits
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GE - Organization 1
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Mr. 'L. C. Koke, is the Project Manager 'of GE for the oyster-Creek reactor. He reports'directly:to Mr.
G.. White,
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- y General Manager,.GE-APED. ;Mr. Koke has been resident at i
d the site now for the past few months.
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Mr. R. Huggins is' the GE principal Project Engineer.
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He reports to Mr. Koke.
He is not resident at the site.
'j He has been-in charge of the GE contingent in their meetings l
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with DRL..Mr. Huggins has been responsible-for approval of GE criteria where these criteria are.used as a basis for i
specifications drawn by a contractor.
He is also responsible l
.for approval of proposed field changes and changes in design' l
specifications.
l In the GE San Jose, APED, Mr. J. Violette was the.
principal Requisition Engineer at the start of this project.
Mr. E. Kratz is the present. principal Requisition Engineer.
j The principal Requisition Engineer. reports.to Dr. R. Richards, i
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Manager of Engineering. Reporting to him are Mr'.
J.' Miller for core design, Mr. P. Bray for thermal and hydraulic design.
j and Mr. R. Lemon for safeguards ~ analysis.
The principal Requisition Engineer is also responsible'for approval of l
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drawings and specifications for the oyster Creek reactor.
The on-site manager for construction,is Mr.' A.
l Dunning.
Mr. E. Wester is the on-site GE electrical engineer j
responsible for seeing that specifications -for electrical l
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p vt work are complied with in the field.
l Mr. K. W. Hess is now on-site'a the GE Site ~
operations Manager.
He is responsible for performing the preoperational tests, for loading and. startup, and operations.
hj supervision for 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> of full power. operation.
Mr. Hess' j
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Results of Visits (continued) r i
l ikjg will have on-site an assistant operations manager, a test
-y engineer, a physics analyst, and five shift supervisors.
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'D The inspector met some of these people during this visit.
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The whole startup crew was expected to be on-site shortly.
J Mr. W. Royce has'been the GE Resident Engineer since j
' 4; startup of construction.
He stated that GE has produced a l
document on quality assurance, but there has been no group at the site specifically and solely responsible, for quality assurance.
He said that design' criteria are established by the GE design group.
For items procured directly by GE, or manufactured by GE, the GE project group transforms.the criteria into specifications. These specifications detail quality control requirements with which the supplier must comply.
F At San Jose, GE APED, there are two groups, who report to the same manager, who are responsible for quality control.
There is an in-house group, independent of production,-
responsible for quality control on GE manufactured items -
fael, control rod drives, instrumen tation.
There is also a vendor quality assurance group of approximately 40 people responsible for quality control of purchased equipment.
They make vendor visits to assure specifications are being met, observe shop' tests and are responsible for processing requests for approval for changes or exceptions.
Changes i
or exceptions must be approsnd by the design engineer responsible for a system dewign and must also be signed -
i off by the principal Project Engineer.
4 j
Direct procurement by GE was principally for the f
nuclear portion of the plant.
Conventional plant items
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were procured through Burns & Roe, the Architect-Engineer.
I Burns & Roe was also the construction supervisor,= and subcontracts for on-site labor were administered by Burns
& Roe.
For conventional plant items and site fabrication, (continued)
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- Results of Visits J(continued) t
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[y GE. wrote criteria and Burns-& Roe transformed th'ese cr1teria L~
into' detailed specifications...These specifications then went 4
through.the same approval process as items procured directly l
- by GE
- that is,.. approval by the GE design engineer'and the j
F GE principal Proj,ect Engineer.
Changes and exceptions j
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were processed similarly. Burns ' & Roe then became responsible l
for quality control for these items..For example, Burns &-
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Roe subcontracted concrete inspection and quality assurance i
to U. S. Testing Laboratories.
Welding quality control has
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been' described by the inspector in a previous report.
l Amaryll-Doyle was the welding subcontractor to Burns &' Roe t
for radiography.
Mr. Royce said that'in~'every case,. Burns.
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& Roe had an engineering inspector responsible for on-sitet approval, and GE also had an on-site
- specialty engineer responsible for approval of final installation.-
l The inspector inquired specifically of. vendor visits for reviewing quality control and witnessing shop tests for I
the main steam isolation valves and the relief and safety
. valves.
Mr. Royce replied that this was handled by the GE.
Vendor Quality Assurance Group and. that duplicate records l
are being transmitted'to the site.
s Mr. Royce said that he understood that JC representa-i tives had made shop visits during.the reactor. vessel fabrica-tion, and had also visited the GE ' shops for ' instrumentation and control.
He thought these trips were more-for familiariza-I tion rather than quality assurance.
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The inspector reviewed a file drawer.of procurement j
i records that Mr. Royce is assembling at the site.
He said i
that original records had not been transmitted-to the site previously for fear a fire in the construction shack would destroy them.
There are few records available at the site at.
this time.
Mr. Royce has sent-out letters to all suppliers, i
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_' Results of -Visits? (continued)
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pfA including his own home office'and Burns'& Roes directing 4
that. copies of. purchase orders, final purchase specifica-
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.tions,~ records of tests.and. quality control, manufacturers' j
data reports, records of shop hydroltests, and ~ alll associated i
correspondence be forwarded to the site'as soon as possible.
l The inspector observed that the. material -received'so far l
5 has been filed =according to a GE or Burns &-Roe specifica--
j 7:p tion number.
Mr. Royce agree,d with the inspector that j
future info rmation retrieval would be easier if the file j
was kept according to plant systems.
This would also. ease l
the. inspector's job of reviewing the file.
Mrs Hetrick later reported to the inspector th at the file format will j
be on a systems basis.
concrete ' quality control was subcontracted by Burns l
& Roe to U. S. Testing Laboratories.
A previous inspection ~
report
- discussed this program.- Record review of this work and other structural quality control by the inspector is j
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being arranged by Mr. -Royce with Mr. Keith Clayton of, Burns
& Roe.
On September 29, there was still' considerable critical.
-t area concrete to be poured.
The essence'of the quality assurance program described above was made a matter of public record by testimony during l
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-the public hearing for the construction' permit'for this l'
reactor.
Mr. R. Huggins of GE has told the inspector that,
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3 in his opinion, the real demonstration of quality assurance will take place in-systems preoperational testing.
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B.
Plant Status j
l Following is a summary of the status of plant systems as of September 29:
(continued).
- CO REPORT NO. 219/66-1, paragraph II.D.
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Results '~of visits (continued)-
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1.
Station Grounding l
4 Major elements have been. installed and checked out.-
.i Individual connections to plant components.are:being
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made as each system ;is subjected to ' construction'
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-tests.
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,2.
.125 volt DC System l
4 The batteries are in place and are being used..
l Temporary construction power is provided to the-battery chargers, since the permanent battery chargers have not been installed.
A separating.
partition between the two banks has not been l
installed.
6 3.
230 KV Electrical System' l
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This system is installed and construction tests-
-f completed.
l 4.
34.5 KV System i
This system is installed and construction tests completed.
i 5.
4160 Volt System r.
Some switchgear in this system has not yet been j g4 put into service.
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480 volt System
-Some control centers in this system have not yet j
been put into service.
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Results of Visits (continued).
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-220 volt and 120 volt AC Systems k'
k The physical equipment of these systems have' been installed, but all construction tests have not lf..
been completed.
The construction tests on a ll fi
-tr i electrical systems-consist of the following:
,k a.
Check continuity and phasing.
b.
Megger all control and power wiring.
c.
Relay tests and adjustments.
d.
Proper operation of transformer cooling and instrumentation.
e.
Check circuit breaker operation.
f.
High potential tests, if required.
g.
Calibration of meters.
h.
Proper operation of all controls.
8.
Make-up Water System 7
This system is installed.
Some instrumentation requires further calibration and adjustment.
Plant instrument air is available to air operated controls.
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9.
Service Water System This system is installed and construction tests g
have been completed.
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Turbine Building Cooling Water' system 7p This system is installed and construction-tests have-1 ?.
been completed.
11.
Fire Water System
.c This system has not_been completely _ installed 1
in that the pond has not yet.been tied'in.
12.
Instrument Air and Service Air These systems are installed but require adjustment of controls and interlocks.
13.
Condensate Demineralizer System-The physical equipment of this system has-been installed and the pump has been operated, but j
resin transfer and regeneration have not'been j
done.
i 14.
Plant Heating Boiler This_ system has.been installed and checked'out.
It was used to supply steam for. the primary system hydro test.
45 15.
Reactor Building Cooling Water System This system is installed and has been operated i
for cooling the process pumps used for chemical cleaning.
16.
Control Rod Hydraulic System This system is._ installed with the exception of the accumulators, which are being installed.
A hydro test and chemical cleaning and flushing is scheduled next before further testing.
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3 Results of Visits (continued) 3
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17.
Fuel Pool Cooling System 1r 1h.
Installation of the stainless steel lining has started on the pool floors.
The pool walls have not been lined as yet.
The heat exchangers and (j
the purification system have been installed
y but have not been operated.
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18.
Fuel Handling System The refueling. platform is scheduled for installation within a. week.
A job crane is not yet on-site, I
but delivery is expected November 1, 1967.
19.
Clean-up Demineralizer System The equipment has been installed.
It has been hydro tested only to the first valve out of the reactor. The -pumps will be used during the chemical cleaning - of the primary system.
j
- 20. ' Emergency Condenser i
This is installed except 23r some valve operators and wiring, 21.
Shutdown cooling System l
di This system is installed.
The system was. used to heat up water for the primary system hydro test.
1 22.
Liquid Poison System l-This system has been installed except for the explosive injection valves.
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Reactor Vessel Safety and' Relief Valves-23.
.. l7 2 These. valves have been installed.
The valves l
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were removed during the primary system hydro.-
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. g The valves were shop' tested and1 adjusted.'
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,3, j Relief valve operation from control room has l
d not been demonstrated.
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Reactor Recirculation Syst'em i
This system is installed.
Pump impellers were removed for the primary system hydro test,n and this. system was included in that hydro. test.
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25.
Core Spray System 1
This s" stem is installed..It is planned to-operate it during the chemical flushing of.the j
c.
~ The high pressure side of this-l primary system.
system was included in-the primary system hydro '
i test.
It'has been operated manually but not f
< t automatically.
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26.
Containment coolina System This system is installed but has-not been operated.-
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27.
Radioactive Waste Disposal System j
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was still being poured on September 29.
Waste E
storage tanks have all be installed.
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Nuclear Instrumenta: ion System
- 1 All components are said to be on hand at the
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site and are being calibrated on the bench.
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There is still considerable wiring to be pulled!
I and terminated.
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29.
This equipment is on-site but has not been-installed.
30.
Diesel Generator One generator is on-site; the second was said to be expected in a few weeks.
The-building i
to house these units has only had its footings.
poured.
t 31.
Emergency Ventilation System I
The duct work is complete but the fans and filters have not been installed.
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32.
Conver.bional Plant Systems a.
-Circulating Water.
f b.
Condensate and Feed Water.
1 c.
Turbine Generator.
The physical equipment for these systems are all installed, but not tested.
The circulating water system has been operated.
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33.
Stack' it" -
Concrete. pouring for.the' stack.is' estimated-to i
c be three-quarters finished.
- This status report is on the; basis of personal ob-
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servation:by the inspector.and discussions with GE and 'JC j
t personnel at the. site.
In discussing ' this status, Messrs.
ll McCluskey and Hetrick emphasized that they did,not consider.
j that any preoperational tests had been performed.. Various electrical and. water systems have been put into partial-operation in order to= work on other systems.L JC has-taken nominal custody of these systems in order that their own union operators may operate these systems for. training without jurisdictional disputes from the' craft unions.
However, Mr. McCluskey pointed out that there' are many j
discrepancies in these ' systems,. especially in instrumai ta-j
. tion, and while -many of these systems have had construction c
tests, no system as yet has had any preoperational testing,-
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GE people on-site maintain that they will be~
.j ready to load fuel on December 15.
Mr..Hetrick, JC',
'Lj stated to the inspector that GE should certainly be-ready in March 1968.
Mr. Woody Riggle, the'JC; Instrument' and Electrical Foreman, who is working closely with GE; and checkout, stated to the inspector that he' does not engineers responsible for instrumentation installation expect GE to be ready until April'1968.
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7 on his tours of the-facility, the inspector.has
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made estimates of the capacities of; equipment' as installed.
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Nothing major has been observed-to be noncompliance with the FSAR, and its amendments.
An exact check of equip-
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ment versus FSAR and license Technical Specifications will_
be made as each system is subject to its preoperational 3
test.
Items which have been observed to require further l
investigati on will be listed below under paragraph II.M.,
Preoperational Test Procedures.
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Wiring
' A discussion was ' held with Mr. Wester, GE Electrical.
1 Engineer, who. is responsible for compliance with specifica--
tions of electrical requirements.
Mr. Wester stated that
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criteria for routing of wiring and separation of redundant,
' O Ni circuits were written by GE.
The actual field routing and
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h tray assignment is left to the contractor.
Each tray
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is numbered and each cable assigned to a tray has a j
corresponding number.
The contractor's route sheet for.
each cable specified the tray and route, and it must be approved by Mr. Wester before installation.
The-Burns &
l Roe electrical inspector is responsible for physically j
checking each cable in its tray or conduit, and.for signing i
the route sheet to attest that each cable is properly located.
Craduit, rather than open cable trays, is used'for-safety.
system wiring from.the sensing element to the' control room.
i The -inspector observed such conduit runs in the cable-room j
3 beneath the con' trol room.
Further spot checking of this-
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system is planned by the inspector.
j D.
Reactor Vessel and Primary System Hydro Test This test had been scheduled for about two. weeks prior to September 29.
A start was made at filling the__ system by i
using the make-up water system.
An agreement had been j
zeached with the craft unions that' JC operators could
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.j operate the system.for training.
Hodever,at-alleged l
misunderstanding developed,. the result of which was.
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that 17 union craftsmen would have had to stand-by. while l
JC operated.
The decision was then made to fill the -
l
_l primary system with demineralized water, from conventional I
JC plants, brought to Oyster Creek by' tank truck.
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Results of Visits (continued) t i
f The test included the reactor vessel, the recircula -
F tion loops, the emergency condenser system, the shutdown cool-j[
ing_ system, the main steam system up to the turbine stop 0
valves, the clean-up system to the first isolation valves, I.'
the entire high pressure side of the core spray system,
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and instrumentation connections to the root valves.
4E Recirculation pump impellers were removed and blank
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flange covers installed.
Blank flanges were installed in place of all primary system safety and relief valves.
Reactor vessel head stud nuts were snugged up.
The system was. filled with water and then vented.
The plant heating boiler supplied steam to the shell side of the shutdown heat exchangers.
The shutdown system was 0
recirculated until 100 F reactor vessel metal temperature was reached.
The reactor vessel head studs were then j
torqued to 0.060 inches.
Thermocouples were installed on the vessel head flange, on the recirculation loops, and at six elevations on the reactor vessel. The metal i
temperature was kept at a minimum of 100 F and a 0
maximum of 140 F during pressurization.
A Heise gauge, 0 - 2000 psig, was installed on one of the main recirculation loops.
The gauge was furnished by JC and had recently been calibrated by a dead-weight tester in a JC shop.
A special hydro pump increased the pressure in the system to 600 psig, then 1200 psig and finally 1800 psig.
All stainless steel field welds had been rubbed with blue carpenter's chalk.
Visual inspection of all welds was made at each of the three pressure stages.
f At 1800 psig, water was found to be leaking down around
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a control rod thimble.
In the original shop fabrication of the reactor vessel, at each control rod location, an internal stub had been welded extending up into dne interior of the l
vessel.
In the field, the control rod thimble was slip-fit up into the stub and welded in place.
Mr.
Dunning stated that 11 weld passes were made on each (continued) l
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'.Y' E h --
- 17..-
74 vb Q~, f
- Results of Visits; (continued)
?
-g
- r thimble-to-stub weld, with a dye penetrant check oni the l
E e
l
~$:
root' pass, the mid-pass and the completed weld.
No-l
_ radiographs were.taken of these welds.
It was stated that the geometry of the situation ' precluded radiography.
Mr.
Dunning _ said' that the similar welds on the Niagara Mohawk l
,L
.,c Power Corporation vessel had similar' quality. control treat-l
[3
^
r ment.
This was also discussed at the DRL-Applicant meeting b
in Bethesda on May 17 and'18, 1967.
l The inspector discussed the leak with Mr. Koke.
Mr. Koke stated thati the leak was in an instrumentation' l
thimble, not a control rod thimble; that all welds had been radiographed; and then he invited the inspector-to lunch on-his next visit.
l l
l The inspector discussed the leak with Mr. Hess.
Mr.-
Hess first stated that GE will repair the leak but will not-.
repeat the hydro test.
He later stated that after the hydro
~l l
they will chemically clean the' system and then; drain it. -
l They will then go_ into the vessel 'and inspect the leaking j
control rod thimble.
The leak may be in either of two j
welds or the thimble wall itself may be porous.
Mr. Hess j
'I said that the thimble will be repaired and if. the ' ASME Code l
requires another hydro test, they will repeat the. hydro.
l E.
Chemical Cleaninq j
l The inspector reviewed a chemical cleaning procedure:
37 to be done after the primary system hydro test.
The procedure i
was prepared by Sumco Inc. of Caldwell, New Jersey, and was a j
a revised edition, dated September 18, 1967.
. i E'
i The procedure was designed for the following systems in the reactor building:
Reactor vessel and reactor recircula '
l t ion loops; core spray system; clean-up domineralizer; reactor i.
head cooling; emergency condenser; reactor shutdown cooling;
[
liquid poison system;.and control rod drive system; and.in~the l
turbine building:
Condenser hot wells, condensate piping; i
i.
f i
(continued) y; f
p v
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. ~
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Results of visits (continued)'
steam ~ jet air ejector; l drain coolers low' pressure heaters;-
cj 'bg.
reactor; feed piping; high pressure heaters; and main-fL steam piping.
I A pipe connecting steam outlets will be installed in-i k side the reactor vessel to isolate the steam system from the s3 reactor water system.
Circulation through the steam system i
will be via the condensate. pumps and the reactor' feed system.
circulation through the reactor sys~com would be via the
)
shutdown cooling system pumps.
j l
The procedure starts with' a preliminary flush with I
demineralized' water.
This will be followed by alkaline
)
cleaning for four hours to remove grease, oil, rust j
preservative and hydrocarbons with a solution of 0.5%
)
Trisodium phosphate and 0.02% wetting agent at 160 -
)
'180 F.
Next, the system will be flushed for four hours 0
with a solution at 170 - 1800F at pH of 9.5 for-four hours of the following:
5% sodium ethylene diamine j
tetra acetic acid (EDTA), 0.5% reducing agent and.
O.02% wetting agent.
This will be followed by6 a flush until the conductivity;1_r! is the same as. the conductivity
.j out, and the change in pH between inlet and outlet is-less-l than 0.5.
The lay up chemical solution will be circulated for six hours.
This solution will consist of the following:
4 0.25% sodium nitrate and 100 ppm morpholine.
The procedure j
specifies that the maximum concentration of chlorides in any j
solution is 100 ppm.
1 e
}
The procedure details analytical procedures for total l
)
alkalinity, oil, free F.DTA-Na4, chiodides, and dissolved j
j ferrous and ferric ion.
The procedure specifies'that data j
j shall be taken every hour during the process, and describes j
l reporting requirements.
l
.t
.The inspector stated to Mr. Hess that the maximum j
allowable chloride content of 100 ppm seemed high.. Mr.
l Hess replied that the process would be done with well j
water which had a maximum of '14 ppm chlorides.
j l
(continued) l l
i
m-2,..
.=__
u_
o 3
]
_ 19 _
I
.l Results of Visits (continued)
I i
F.
Training
[
' $b The training program for plant personnel has been described in the FSAR.
Mr. Hetrick is in charge of this program.
He keeps a bar chart of each man's progress. The inspector has reviewed this record and has discussed the s
p program with Mr. Hetrick.
Operating personnel training is up to date.
Operators are presently standing watches in the control room and are operating systems as they become available during construction tests.
Shift foremen and j
some operators are writing detailed operating procedures.
G.
Personnel i
The plant organization has been described in the j
FSAR.
The inspector has observed that the description is
+
true.
The following information is pertinent.
Mr. Dan Howard, dae Technical Engineer, left JC I
in January 1967.
It is not presently planned to replace him.
i Mr. Ivan Finfrock, the Technical Supervisor, is not resident at the site.
He spends approximately three days per week at the site.
He is in charge of environmental monitoring, 'and spends much time in dealing with regulatory l
agencies other than the AEC.
1 I
The Shift Foremen and A and B operator positions are filled by men with previous reactor operating exper ience.
f I
There are four Chemical Technicians - Messrs. W. J.
Neuman, R. E. Petersen, K. B. Hemming, and D. R. Murphy -
reporting to Mr. Richard Doyle, the Chemical Supervisor.
4 i
(continued) 1
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- m.m m.4 me.m %
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3 I
C y 1
Results of Visits,(continued) t 6V -
E-There are two Radiation Technicians - Messrs. J.
P.-
?
Cook and J. W. Scull - reporting to _the Radiation Protection b
- Supervisor, Mr. D. Kaulback.
I g
The Instrument and Electrical Group consists of p jy foreman Elwood Rizzle, instrument man H. S. Logan and l
r electrical maintenance man J. D. Brown.
t The Maintenance Supervisor is Mr. Norman Nelson.
He is a year or two away from retirement. He maintains a home at a considerable distance from the plant.
He lives i
locally during the week, going home over the weekend and sometimes during the middle of the week.
Mr. Fred Kossatz is the' Mechanical Foreman, and working for him is one i
mechanical maintenance man, F. A. Anderson.
H.
Health Physics During the visit, the health physics procedures manual was at the printers and was not available for review.
Survey equipment is on order but none is yet on hand.
Physical examinations, including urinanalysis, have been
- i given to plant personnel.
Whole body counting is not j
presently proposed.
Messrs. Kaulback and Nelson have decided that the i
plant shall have both a hot and cold shop, each with its own set of marked tools.
No spare penetration for a welder inside containment is planned.
Mr. Nelson said that he has
+
never seen freeze plugs used as a maintenance technique I
for blocking a line anywhere in the company, and he does i
not intend to use them.
Mr. Nelson also said that the plant air compressors have teflon rings, but do not use regular turbine oil in the crankcase.
He said that they had had poor experience with synthetic oils.
t (continued) i
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j' (continued) 1
' Results - of Visits a
ly
.i w
.E i
J.
Radiation Emergency Plan t
-i
- This plan has been described in the amendments to the FSAR and is presently being evaluated by New -Jersey
]
authorities and DRL.
The: implementation of the plan.in 4
its final and approved form will be checked.by the inspector.
e At the present, the inspector notes that' the evacuation route
]
arrows have not been installed.
s..
K.
Fire Protection Systen
{
't
't This has been described in the FSAR.
Its installation l
will be checked in future visits.
The inspector. notes that l
JC does not plan to install smoke or gas detectors and alarms
.in cable spreading areas.
L.
Procedures t
As a condition of its contract', GE is supplying.to JC a design manual which is a narrative description of how
^
the plant works, a procedures manual, and two volumes of.
j c
preoperational test procedures, but GE does not supply -
l operating procedures.
TheLJC operations Supervisor, foremen
'I and some operators are writing operating procedures' on the l
basis of the documents that GE did furnish.
As of September.
29, Mr. Hetrick said that the job is almost half' done.
No
,{
emergency operating or equipment malfunction procedures have been developed as yet.
]
7-i Chemical and maintenance procedures are being l
developed but are not yet ready for a comprehensive review.
i Mr. Agon, Assistant Technical Engineer, has taken i
a four-month nuclear engineer's course at'GE.
The inspector
.l reviewed a manual that he is developing on the basis of
.j 7
this course. It will cover the following topics:
core
]
(continued) i t
l 5
}
~.
. f
j 8-
- - ar.eet t
W4Mnema' m
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1 4,
4.-
2.-
A
- 22~-
.jj Results'of Visits (continued) i 1
1
,Jh i
J-A calculation, power distribution, shutdown margin, TIP 7.g calibration, APRM calibration, heat balance, control rod j
.y-depletion, critical heat - flux ratio, control rod pattern -
j ;
. calibration, control rod interchange, reactivity measurements, l-TIP normalization, and fuel cycle length.
j t
.a MNb j
Y M.
Preoperational Test Procedures y-1 GE provided two.large volumes, each as large as Volume
-l I of the FSAR,. of preoperational test ' procedures.
Mr. McCluskey I
d.
allowed the inspector to take these volumes off-site-to revi ew l
the procedures in the quiet of a motel room.
The JC, GE and
{
Bur ns & Roe site personnel are still housed in the small, j
cramped, noisy construction shacks.
The inspector reviewed all' of the test procedures _
once completely, and reviewed about two-thirds of the j
procedures a second time taking notes.
It was planned on.
j the next visit to continue this review.
Some ' of the inspector 's j
notes on specific tests are included-below.
It may be noted
.l that some of the inspector's notes are identical to informa-tion contained in the applicant's amendment No. 11, dated i
september 5,1967, which had not-been forwarded to the.
inspector at the time of his review.
In his review of the l
test procedures, ' the inspector noted no major " items on which l
there might be a difference of opinion between' the applicant and the inspector on.the. adequacy of a test.
The word " major" l
is used in the context of. time-consuming.
It was observed that relatively few of the test procedures had been approved j
~
by a JC representative.. Mr. Hetrick told the inspector j
that he has not completed his own review and so has not l
I signed off on the tests.
l
}.
k-Each test has a cover sheet which has the title j
of the test, by whom it was prepared, the date, and a space for revisions noted.
There are spaces for approvals by-
~!
(continued)
+ --
s
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Results of Visits. (continued) j t a
(
a
' ^
.....n 3'
.GE Operations Manager
.i
,1 GE Plant. Test Engineer GE Proj ect Manager.
l Burns & Roe Project Manager i
k-
-Burns & Roe Manager, Plant Test'& Operations-j JC Representative
]
E ly.
r~
Test completion. is certified by the ' following:.
]
Test Completed By:
Operations Superintendent, ' GE
);
Approvals Test Engineer, GE Test Engineer, Bu rns & Roe Operations Manager, GE Representative of JC
(
'In each test description, there is a purpose, references (to drawings or manuals), prerequisites, test j
description, special test equipment, a nd data. sheets.
J i
Following is an up-to-date list' of preoperati~onal tests:
I A-1
. Dry Well and Absorption' System if A-2 Reactor Vessel Components' A-3 Safety and' Relief Valves 0
A-4 Primary System Expansion j
l A Control Rod Hydraulic Drive System-A-6' Control' Rod Drives s
If~
A-7 Recirculation System and'M.G. Sets j
A-8 Emergency condenser
]
A-9 Reactor Shutdown Cooling System-
]
a A-10 Reactor Cleanup System A-ll Poison Injection System j
A-12 Core Spray System 7
A-13 Containment Spray System A-14 containment Inerting l
A-15 Fuel Pool Cooling l
A Fuel Handling Equipment i
A-17 Reactor Head Cooling 1-(continued) i e
.:?L4 a :.
^
~-. -
9 3
u
.r Results of Visits (continued)
B-1 Turbine oil System
]yf B-2 Turbine Control B-3 Steam Cycle - Pressure Regulator and Gland
~
{
Exhaust and Reheater and Reheater Probaction B-4 Generator Cooling B-5 Main and Spare Exciter ty C-1 Condenser and Auxiliary Hotwell Vacuum Pump.
{
C-2 Condensate and Feed Water C-3 Cooling Water System C -4 Service Water System C-5 Condensate Demineralizer C-6 Make-up and Domestic Water System C-7 Turbine Building Cooling Water C-8 Reactor Building Cooling Water C-9 Instrument and Service Air System C-lO Fire Protection System C-11 Plant Heating Boiler C-12 Vents - Turbine, Reactor Radioactive Waste, Access control Buildings C-13 Dry Well Vent C-14 Stand-by Gas Treatment and Reactor Building Leak Rate Test C-16 Liquid Radioactive Waste C-17 Solid Radioactive Waste D-1 Station Grounding D-2 125 volt DC D-3 230 KV Electric System D-4 34.5 KV System t
D-6 480 Volt System
~'
D-7 220 - 120 Volt AC
'[
D-8 Emergency Diesel D-9 Plant Communication System D-10 Feed Water Heater Control D-ll Feed Water Controls D-12 Reactor Protection System D-13 Neutron Monitoring System (continued)
- - - - = - - - - - - - - - - - - - -
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ph Results of Visits,(continued) r.l
-i
.c.,
g%:
D-14".TIP. Calibration. System
- D-15 Process Radiation Monitoring d
D-16 : Area Radiation Monitoring D-17' Off Gas and Stack Monitoring g.[ [1 D-18 Environmental Monitoring D-19 Rod. Worth Minimizer i~
- lw cr.
l1 t
1.
A-1, Dry Well and Absorption System Leak 5.
Rate Measurement p:
This test' consists of two distinct phases.
g 1
First, the dry well and absorption chamberLare retested to their respective design pressures, 62 psig and 35 psig to proof test..all' piping and electrical penetrations and expansion ' joints that have been-installed since the initial overload and leak rate test.
Following these tests, the downcomers will be _ uncapped.
E The second phase of this test. is a leak rate test on the combined dry well and absorption system, and separately on individual penetra-tions.
The torus will be-flooded to its
I normal water level.
The electromatic relief..
valve' discharge piping must.be completed and either blanked off or connected tightly. to the relief valve discharge flanges.
The vacuum-g['
valves.must'be capped or~ removed and the con-t nection plugged.
If investigation indicates j
that the expansion joint will not withstand 62 psig' external pressure, valve discharge-piping must be open to the dry well' and blanked
'm with a temporary cap in place of. the canalefitting.
-l This cap would be removed and replaced with the-l p
(continued) 1
_-__.__._--___.-___.m_____-____m
____._2
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~
J (i::ontinued) i Results of' Visits 1
i 4
_ft '
canal fitting at the same time -that the.downcomer 91 caps are removed.
During-the : leak' rate test,u the reactor vessel should be filled with' water to!the j _
operating ' level.:' This would be the' condition.
M 4'
during. all subsequent leak rate -tests.
The N.:
vessel head should be'off or the vessel vented -
- I to the dry well by removal _of the heat nozzle flange.. If the above conditiona cannot be met during the 162 psig and.35 psig proof test, the -
reactor vessel head should be in ~ place.
The-5 drive mechanism should be'in place:during the 62 psig and 35 psig proof test to permit a~ normal water-fill condition in the hydraulic: system with' all check valves 'and solenoid valves thereby exposed to a water' seal.
A leak rate measurement will be'made on the.
penetration and seals using a nitrogen bottle or supply from the instrument-air. system, to pressurize the volume to 35 psig.
Thermometers will be attached to the piping surface and temperature and pressure will be recorded ' over a period of several hours.-. Leakage' rate data must be taken at.relatively constant ambient.
temperature and extrapolated for ' a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period.
The pressure holding period may range from:1 hour.to 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s-if required to obtain meaningful data.
Measurements of leakage rates
-i will be taken of the following components:
I
-l a.
Dry well head gasket.
b.
Torus manhole hatgh gasket - north.
y.
c.
Torus manhole hatch gasket - south.
E d.
Airlock.
(continued)
Q c s.
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x.- )
I-Results of Visits,(continued) i I
w.
' l(,
e.
Equipment hatch (airlock) gaskets.
- tm I
f.
Main steam expansion bellas - north line.
d~'
I p
g.
Main steam expansion bellas - south line.
Jh h.
Feed water expansion bellas - north line.
I 1,
Feed water expansion bellws - south line.
j.
Electrical penetrations - pwer cable, j
i 4
k.
Electrical penetrations - control wiring.
1.
Electrical penetrations - coaxial.
i m.
Electrical penetrations - triaxial.
j Note:
Isolation valves - operational - and leak rate tests.
For completeness, all; isolation valves will be listed in this test procedure, although the required test may be covered in the appropriate system preoperational.
In such case, valve stroking times, recording opening and closing times may be
{
copied from the other preoperational test data-sheet.
t
}
Next there is a combined leak rate test of the i
dry well and torus. - The d ancomer caps are h
removed and the water in the torus is brought to normal water level.
The pressure in containment will be raised to
{
20 psig and recordings will be made of the atmospheric temperature, the barometric pressure, e
s (continued)
T m
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- 28'-
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Results of Visits icontinued)
. L-k;'
the dry well gauge ' pressure, the dry well
_ y absolute pressure,. the difference :in pressure y
between:the dry well'and the reference-system, i
the internal air. temperature, the internal
- p -
water; temperature in the torus and the reactor Op vessel, and the internal dow1 point temperatures in degrees F..
.{
Measurement-of the core spray. and containment spray pump seal leakage will be' made during the leak rate-test by arranging drip pans or ob-serving. drip rates.
The following points are checked:
Pump: flanges, pump mechanical seals, heat exchanger flanges, check valve covers, and valve stem packing.
The method of calculation of leak rate, with corrections for moisture, is. included in the test procedure.
1 2.
A-2, Reactor vessel components This test includes testing reactor-vessel thermocouples, proper setting of reactor = vessel stabilizers, stud tensioner operation, and a.
4 test of vessel seal leak detection instrumenta-tion.
This test will be run in conjunction with test A-9 to establish vessel heatup rate.
e Stabilizers are installed in pairs'and each is provided to allow axial and radial expansion of the vessel while providing support for it during any earthquake disturbance.. The stabilizer, d.
when' properly set, requires a setting-of 106,000 pounds.
Each. assembly contains a calibration scale to properly set the required load.
(continued)
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Results' of Visits -(continued) r t
,,, (
1g' ;<
i W (
The stud tensioner operation has.been~ demonstrated-
,p4 prior to the reactor vessel hydro.. ' They were '
j is:
observed.in use by the inspector.
There_are four-1 M
stud tensione,rs, als'o a square lifting ring.
9A To test the reactor vessel' seal: leak detection' l
3, instrumentation,, a dead weight tester' is used..
- i 4-3, A-3, Reactor Vessel Safety, Relief and Main j
i Isolation valves No tests of the reactor safety valves are planned.
at the site.
They have been - factory set and will l
be installed as received.
The safety valves.
j may be removed periodically for off-sit'e verifica-l
' tion of set points as required by plant procedures..
l
+
~
A temperature response of the safety and relief valves discharge lines will' be.made by using a soldering -iron' to apply heat to the thermo-couple.
The relief valves will be operated.
j manually from the control' room.
Check proper
.j operation of piston operated-valves from test j
pressure signal to reactor pressume sensors..
Main steam line isolation - valves will be' manual.
j operated.
Further tests will take place when -
reactor steam is available..
~]
ll i
4.
A _4.
Primary System Expansion Test l
t i
.l
Purpose:
To verify that these portions of the l
l primary and auxiliary systems which are located -
1 in the dry well and are subject to a1 range. of temperatures, are designed and installed so that-l 4;
there are no. undesirable high stresses resulting' I
-i (continued) l l
. i
a w.
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~
W Results of Visits (continued)
I
- r.
from system thermal expansion.. The test also' x 4i tests elements of the~ primary system - packing,
. gasket for leakage at full operating pressure; i
f[
and temperature.
It includes a full flow range' l
y
<1 i test of the. variable ' speed recirculation pumps,-
.l
[
end evaluation.of design. adequacy.;of the dry
.[
well ventilation system.
It is necessary to perform.other tests in conjunction with this one. -Recirculation. flow control,-l-pump per--
formance, dry well ventilation system,; reactor
]
water level indication, and head cooling. system h
}
may be. tested over the operating pressure andf temperature. range if those tests are-coordinated with this'one.
Therefore, ;it.will be necessary l
to issue a coordinating procedure.
Undesirably high component stresses may result
~
' when the free movement of'an~ expanding system ~
is restricted.
This. restriction may result from l
i improper design, or incorrect installation. 'Im-properly placed. hangers and. supports may result j
in. interference of the expanding system With j
I other objects.
To demonstrate the thermal expansion character-
)
istics of the Oyster. Creek reactor, primary.
j system temperatures will be raised from ambient.
j to rated.
This may not require nuclear heating
)
and will be accomplished in the following sequence:,
[
f O
a.
Ambient to 3OO F.
Two sources of heat will-be used.
One of the five recirculation pumps will-be operated.
Heat addition of l
all five pumps-is rated at 3.7 Mwt.
In.
3:
l addition, the shutdown. cooling system is (continued)
J, g
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. ~
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i ';
i- >
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Results of Visits (continued) i, q'~
. [
a source of heat with auxiliary steam passing through the shell side of the shutdown heat exchanger and reactor water passing through f n c,i l the tube side.
The maximum. temperature w
allowable for the shutdown cooling system j-use is 350 F.
Since the heating steam is 0
0 limited to 75 psig (305 F at saturated),
this limit will not be reached, l
l 0
I b.
The next phase is 300 F to 545 F.
The shut--
down cooling system will be taken out of service at about 3000
. Further heating will be fur-nished by the recirculation pumps alone.
It is expected that they will be capable of' raising the system temperature to rated in a reasonable period of time.
Displacement of components of the primary system will be checked by visual inspection while the system.
is at temperature.
At given points, dis--
placement will be measured.
Visual in-spection will be made at incremental rises 0
of 100 F and will include the primary system
}
and connected auxiliary systems.
This test j
procedure includes a list of specific items i
to be checked for noninterference:
l (1)
Control rod drive thimble.
I (2)
Control rod drive housing support.
l (3)
Recirculation loops.
(4) ' Sample and instrumentation lines.
(5)
Primary steam ' lines.
t j
If the primary isolation valves are closed, the temperature of'the steam line piping (continued)
I
.. ]
. T.
'? L -
^*
- n o
3 M
i.
i Results of Visits (continued) kt -
a source of heat with auxiliary steam passing Fj through the shell side of the shutdown heat exchanger and reactor water passing through the tube side..The maximum temperature g
allowable for the shutdown cooling system
?}
use is 3500F.
Since the heating steam is 0
limited to 75 psig' (305 F at saturated),
this limit will not be reached.
0 b.
The'next phase is 300 F to 545 F.
The shut-down cooling system will be taken out of service 0
at about 300.
Further heating will be fur-nished by the recirculation pumps alone.
It is expected that they will be capable of raising the system temperature to rated in a reasonable period of time.
Displacement of components of the primary system will be checked by visual inspection while the system is at temperature.
At given points, dis-placement will be measured.
Visual in-spection will be made at incremental _ rises 0
of 100 F and will' include the primary system and connected auxiliary systems.
This test procedure includes a list of specific items.
to be checked for noninterference:
f (1)
Control rod drive thimble.
(2)
Control rod drive housing support.
e f
(3)
Recirculation loops.
I (4)
Sample and instrumentation lines._
i (5)
Primary steam lines.
1 If the primary isolation valves are closed,-
the temperature of the steam line piping j
i (continued)
I
a,,
._a. a _.. _
Q ) p,- s +
,lJ;,.
.+
p 3 :. m o
3 a
.4 i p.
Results of Visits (continued) t l
f;
~
4 a source of heat with auxiliary steam passing, 4
through the shell side of the shutdown heat exchanger and reactor water. passing:through-t-
! i the tube side.
The maximum temperature Q-N allowable for the shutdown cooling systemL use is 350 F.
Since the. heating. steam.is 0
]
0 limited to-75 psig (305 F at saturated),
this limit will not be reached.--
0 b.
The next phase is 300 F-to 545 F.
- The shut-down cooling system will be taken out of service l
at about 300.
Further heating will be fur-0 L
L nished by the recirculation pumps.alone.
It is expected that they will be capable of raising the system temperature to rated in
~
a reasonable period of time.
Displacement' of components of the primary system will be checked by visual. inspection ~ while the system is at temperature.
At given points, dis-
- i placement will be measured.
Visual in--
spection will be made at incremental rises C
of 100 'F and will-include the primary system ~
and connected auxiliary systems.
This tests procedure includes a list of specific items to be checked for noninterference:
(1) control rod drive thimble.
~
4/<W (2) control rod drive housing support.
(3)
Recirculation loops.
I.
{
(4)
Sample and instrumentation lines.
(5)
Primary steam lines.
If the primary isolation valves are closed, the temperature of the steam line piping (continued) bA as ie i-i sus isi
~
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}
9 1 l s
Results of Visits (continued) y n
1: A
'?
. er t"
would decrease.
The resulting pipe movement j
~
j.
should not be different from the predicted
)
values.
Contact' thermometers should be' l
f used to find the, temperature distribution l
~
i
.2 J along the pipe length and this :information -
. will be used in evaluating the test results.
I An optical device shall be used.to' verify
- that the recirculation pump shafts are oriented.
properly within specifications,at rated condi-tions.
The recirculation pumps'and motors are given an initial offset - to compensate' for tilt of the pump bowl during heatup.
l Auxiliary systems will' be checked for proper suspension at rated conditions. : The test procedure states that in.the preoperational
{
test it may not be possible to simulate full process conditions for all systems.
The procedure also includes a memorandum.
j l
on the calculated and predicted amount-of thermal expansion of the primary steam system and the recirculation loops for an. increase l
from 700F to 575 F.
The procedure also j
0 describes the spring loaded stylus to'be 3
used for following component expansion.
j Stylus movement will be recorded on a -
Sanborn recorder.-
f,*
5.
A-5, control Rod Drive' Hydraulic System 1
4
}
Construction tests 'must have been completed
)
l on the pumps, motor and electrical switch gear.:
i The gear box and reservoir must be filled with f:
oil.
The suction screens must be installed'in the cooling water system. 13ue motors should have been bumped in: proper rotation.
Control room instrumentation must operate and indicate correctly.
(continued)
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4 Results of Visits (continued) h,g.
Scram valve testing:
The hydraulic control units
.' c!
must be. tested with the charge accumulators' to j[i verify that the scram discharge valve opens a minimum-of 10 milliseconds before the-inlet-valve opens.
A data sheet is provided for 3
- g recording this data.
Time required for limit switch actuation will be recorded.
In this
+
test procedure, it is assumed that a full complement of blade guides will be available for the test.
If this is not true, the test engineer shall modify the' test to accommodate the number of blade guides available.
Caution:
During drL ve testing of a drive system, the drive withdrawal isolation valve must never be closed while the inlet isolation valve is open and the accumulator charged. - If -
the drive should be inadvertently exposed to accumulate pressure with the vessel depres-surized and the drive withdrawal isolation i
valve closed, the drive sould be subject to i
damaging high pressures which would necessitate replacement of the drive.
l a.
Drives are inserted and withdrawn to adjust travel speed to 3.0 1 0.3 inches per second or 43 to 53 seconds for a full stroke in t
if either direction.
After initial speed adjustment,.each drive is cycled in and out five times, and the insertion and withdrawal times recorded. It may be desirable to optimize the timer contact
. set points.
)
-R (continued)
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Results of-Visits -(continued) l
'ns l
I a
b.
In-scram ' testing, each drive will:be scram
- tested and timed three times and then the total system of 136 out'of the:137 drives.
will be scransned. from a trip signal. from l
[
the scram discharge' volume high water level t
sensors.
The.following data will be taken'..
.k 3
(1)
Scram timc.
.. l l
(2) 90% insertion time on a%few randomly selected drives.
1
^
(3)
Pump flow during accumulator charging.
to determine. maximum pump flow.and current.
j (4)
Accumulator charging time.
l
-(
J (5)
Accumulator. charging time after resetting?
j the safety circuit.
i
}
-(6)
Discharge volume draining' time.
i I
- 6. - A-6, Control' Rod Drive Manual Control-This test is intended'to demonstrate.that-inter-.
locks, and alarms, and indicators - are functioning l
i_
37 correctly.. All wiring must have been completed
--l prior to this test.
All sensors must'be..in-
. j stalled.
The rod worth minimizer will be' checked -
separately in preoperational test D-19 and may be bypassed. for this test. 'The' neutron monitoring l
instrumentation may not be fully-operational at '
l
.this time.
Consequently, it will suffice. to l
,t 1
(continued)
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i Results of Visits (continued)
L
-p9 check withdrawal interlocks from-the neutron
~
instrumentation trip units.-The neutron monitoring instrumentation will be tested under.tdue. following guidelines s l
., ' {r Interlock contacts for each instrument' will o,
' h be tripped-to verify that the rod block is j
actuated.. The trip contacts 'will; be manually-manipulated or an electric signal will simulate 1
the detector output trip signal'.
The intent is to afford flexibility in the test program to-
- l accommodate work being done on the' neutron monitoring instrumentation.-
j i
Relay logic test:
Prior to performing this test, the refueling cranes must be functionally tested and operable.
This completed the control rod withdrawal i
interlock portion of the manual controlsystem.
j Rod selection verification test:
Each drive will be selected and given a notch-out signal
. i I
to verify correct wiring to the proper directional solenoid control valve.
j 4
There is also a position indicating system test for each rod drive.
j t g.
7.
A-7, Recirculation System and MG Sets
]
This test is intended'to demonstrate operation
. i L
of pumps, motors, valves, MG sets, and flow-
' j control instrumentation.
The test method is to test the pumps together over the speed
- range permitted by the recirculation system i
(continued) i I
J i
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Results of Visits (continued)
. 63i j
temperature - load limitations.
The-recircula-j
' tion system pump energy will be used in con-junction with the shutdown cooling system to
}
increase the primary. system. temperature and pressure to rated conditions without nuclear
+
I heat.
The recirculation pump may then be tested t
at full. flow conditions.
The preoperational test.
will be used to verify the system interlocks, operating procedures will be checked including the procedure to remove individual pumps,from service while continuing operation with the remaining pumps.
In initial _ operation, the couplings will be disconnected and cable lugs disconnected on each pump, and each hooked up sequentially as each previous unit is demonstrated satisfactorily. Associated tests which will be performed with this test include vibration measurements, primary system expansion, and dry well ventilation.
Items which must be completed prior to this I
test include the following construction items:
Checking alignment, cleaning, lubrication, hydrostatic testing, valve test, ringing wires, i
meggering, etc.
In phase two, various combinations of pumps will be operated together with sequential startup and increase of flow.
Sequence pattern established j
by the evaluation of this test will be followed in the na gular operating procedure.
Also, the i
master speed control will be used after the first i
pump is increased beyond the minimum flow'for the master limiter.
Each subsequent pump will be (continued) i
l
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Results of Visits'~ (continued) f
!?
i
,.i started using individual unit ~ manual speed' f
4 control until transfer can be made to.the master controller.
Normal startup procedures-j will be evaluated after all five pumps are d
gg operating.
The master controller will be used-9 f%
to evaluate response ^by making step changes.-
E,:
Normal shutdown, loop isolation; and restart will I
be performed on single pumps to evaluate these t
procedures.. A one-pump-trip will be-performed
}
to measure normal coastdown.
Then a group _ of
]
j I
pumps on one auxiliary bus will be tripped-and
~
finally all five pumps will be tripped, with
-both of these trips from a simulated-loss of-auxiliary power.
The shutdown system will be operated to maintain.nearly c,onstant:.
1
- 20 F of starting reactor water temperature. -
0 In phase three, the pumping energy to the.
- recirculation system wil1~ be utilized to 'in-t crease the primary system temperature and-pressure to rated condition.
This' permits-
)
3 system expansion measurements _and hot pres-
)
i surized leakage tests without requiring nuclear j
'{
energy.
The dry well ventilation system can be
[
checked at nearly maximum operating. conditions'.-
i The recirculation' system can be. tested at higher j
flows.. The hot startup of a recirculation pump; t
can be -evaluated,1which is. the most serious con-
)
4'f~
dition.
-)
8.
A-8, Emergency Condenser No details are given in this procedure._ In-struments have-to be calibrated previously. ~ Test?
-)
3 procedure includes automatic system initiation.of' the motor operated valves and isolation operation m
of manual override.
(continued)
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Results of Visits- (continued)
{
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+
l 9.
A-9, Reactor Shutdown Cooling System j
Valve. tests, valve interlock tests, valve-j$-
position indication, _ pump operation, minimum i
I flow recirculation, throttling flow, reactor
%1 lj heating, and cooling tests, - are included in :
.j
[
this procedure.
10.
A-10, Primary Clean-up System l
The purpose of this test is to demonstrate 'that l
pumps, interlocks, etc.,_ function properly; that
]
resins can be transferred into and out of the.
demineralizer; and that filter material can be j
coated and removed from the filters.
l
..a I
11.
A-ll, Liquid Poison 1
Pump and valve control instrumentation will _be tested as individual components ' first, and then'
'~
the system 'as a whole will be operated to.
-j demonstrate compliance with design parameters..
.i l
Part A Test entire ' system including inj ection '
into the reactor, using demineralized' water, j
'l i
Part B:
Test the-poison solution preparation
)
jr procedure. 'Amongsttthe precautions _is to prevent
-j inadvertent : firing _ of the explosively ~ actuated valves.
The firing circuit should be disarmed by removing fuses until such time as it'is' l
l
'l necessary to checkout the electrical ' circuit'-
and fire one of the squibs.
-]
g 12.
A-12, Core spray system i
This system with associated automatic depres-l surization, constitutes the low pressure i
(continued) i
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d, Results of Visits ' (continued) i.96
.y standby. core cooling system. - This systen'provides -
{
an alternate-supply of reactor cooling water ~ to
- W prevent fuel clad melting from the improbably.
j
- occurrence.of a pipe break accident in the reactor primary system.
.The purpose is to.
4 7
demonstrate system' operation inl automatic mode Y
by' lowering; reactor. water. level-to trip the
~
lo-lo 1evel switch.
system operation is.
l
~
demonstrated with the following simulated failures:
.i a.
Main pump failure simulated.by opening the
}
circuit breaker to the affected' pump.
b.
Booster pump failure simulated by opening the circuit breaker to :the selected pump.
1 The system will be operated on emergency power bp.
j repeating the former tests'through an inter-
^
ruption of the normal plant power supply of the
. 4160 Volt buses and automatic. pickup of the loads by the 'iesel generator.
This test is
-l d
j done in conjunction'with portions of the j
diesel generator and containment cooling
.l system test.
There is also described a leak ~ rate test on the low pressure side.-
djg The inspector noted that the. test procedure for i
this test needed considerable ' revision to demonstrate -
j.
capability to operate in all modes of alternate
~l supplied of both water and power.
j
'i
^
- 13. -A-12, containment-spray system i
No details are given in the test procedure.-
3 l
(continued)
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Results of Visits (continued) t i
t
.4' 14.
A-14, containment Inerting A caution note is given with this test-to avoid
-( t dead spaces in the dry well after purging.
In-
,)
spectors should operate in a1 buddy system.
gy p 1
6 However, this system will be checked out with
^
i 250,000 cubic feet of. nitrogen.
JC calculates that 1,000,000 cubic feet purge is necessary.
to get to 4.9% O in building.
The-reactor 2
vessel head must be on; the torus full of 1
water. This test should be done after the containment leak rate' test.
15.
A-15, Puel Pool Cooling System 4
Demonstrate filter and demineralizer operation.
Flooding to be done as construction pool leak
(
t e's t.
16.
A-16, Reactor Refueling and Servicing Equipment k
Functionally check each component in: dry runs.
i i
Use JC operators for training. Hood cells, electrical interlocks will be checked.
17.
A-17, Reactor Head Cooling System
- i#
Check pump, valves, controls, and instrumentation..
Evaluate system performance in monitoring reactor vessel water level in conjunction with cleanup-system blowdown.
Demonstrate system performance.
in assisting to maintain reactor vessel tempera-ture differentials wi, thin limits du, ring cooldown j
of vessel.
There is a detailed procedure for this test.
(continued)
I i
..?
ge,
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o 3
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_ 41 -
. i; Results of Visits (continued)
R a)
C' 18.
C-6, Make-up and Domestic Water System 1
[
Straight-forward, detailed procedure is-described.
q s
19.
C-7, Turbine Building Closed Cooling Water System
.]...
Straight-forward, detailed procedure is described.
20.
C-8, Reactor Building Closed Cooling Wat er System Straight-forwar d, detailed procedure is described.
21.
C-9, Instrument and Service Air System I-For test purposes, the air system is assumed to terminate at the pressure reducing station i
or the operating control of the system using the air service.
)
22.
C-10, Fire Protection System t
I Engines, motors, pumps, piping spray nozzles, con-trols, and interrelations to the elevated storage a
tank are to be checked.
Components are:
1l-Qfi'#
a.
Elevated water tank. -
b.
Diesel driven fire pumps, 2000 gpm, each with automatic control system.
j c.
One pond pump.,
\\
(continued) j i
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- V Results - of Visits (continued)
. k nOf-d.
Three deluge systems:-
(1)
For the main transformer, auxiliary transformer and hydrogen bottle storage l
t ne r
area.
- v y
-{
(2)
For the main transformer, startup
=
^
transformer.
l t
(3)
Turbine oil tanks, hose stations, hydrants.
e.
Sprinkler system No. 1 for the seal oil unit and lift pumps, and sprinkler system No. 2 for the turbine room oil equipment,.decon-tamination laundry room, oil lift pumps, r
and oil purification equipment.
The diesel fire pumps have a battery start'and the batteries are on a static charger.
Interlocks, automatic controls for starting and remote e
controls will be checked.
Certainareaswill'beprovidedCo$e,CO dry. chemical and other hand operated units.
.T 2 Purge and fire protection system for the generator
+
l and exciter equipment is covered elsewhere.
l Fjh I
~' '
Certain of these tests will be simulated:
S "d3" deluge above will be tested by simulated; "di" and "d3" deluge alone will be live-tested. -
23.
C-ll, Plant Heatina Boiler The purpose of this demonstration is.to prove j
capability to provide continuous steam
- for the l
plant heating system, reactor shutdown heat exchangers and the concentrated radioactive waste l
tank.
I J
(continued) 1 y
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y Results'of Visits (continued) 714 S
1 Detailed procedures are provided for placing f
[
boiler feed pumps on-line for a hydrotests; 1
flamed draft test, for atomizing air compressor i
%f checkout;. fuel oil pump test; boiler trips;.
~ !
[ir testing of safety valves, distribution' system; l
{
combustion testing for fuel air ratio; soot I
blower and feed water regulator tests.
. i 24.
C-16, Liquid Radioactive Waste System i
Piping,; electric service, floor drains, jn-
. ]
strument air, and instrumentation on waste l
collector subsystem, floor drain collector' subsystem, chemical subsystem, and miscellaneous subsystems must be.rendy.
Procedures are~ ~
l described.for valve tests, pump tests, de-j mineralizer test, filter back wash, ' condensate '
l transfer system, and domineralized water transfer l
t system.
)
i 25.
C-17, Solid-Radioactive Waste System
}
Items. which will be checked include the folloaings.
Hydraulic press, concrete mixer,- centrifuge, i
drum conveyor, storage system,._ fork' lift truck,.
drum filling aystom, hopper, hopper discharge, j
(.c4 feed control, valve mixer, drain valve, mixer i
L discharge, capping machine, : remote controh,
viewing machine, level transmitter, waste. con-centrator preheater,' waste concentrator. con-denser, concentrated. waste tank, ' spent. resin,
l
]
tank, spent resin pump, filter. sludge. pump, l
and all controls',
t I
i (continued) j 6
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44 _
,4 Results of Visits (continued)
-yy 265 D-1, Electrical Grounding System A tinned copper ground grid with ground rods-interconnected in. grid fashion with tinned copper cable is installed under~ the mat of
~'g.
each of the major structures. such as the > turbine; 7
I building, reactor building, radioactive waste t
building, intake structure, and the stack.
Tapped cable connections are made between the ground grid cables and the structural steel co'lumns to ground the station steel structure.
Ground cable taps are brought up from this grid at various points around the periphery of'the station to connect to external plant equipment such as the startup-transformer, main transformer, auxiliary transformer, substation, ' and transmission-1
-line.
cables from the ground grid are connected I
to the plant copper ground buses from which con-nections are made to the generator frame, switch-gear ground buses, motor control centers, etc..
1 There are two. methods of equipment ground used in the generating plant.
The 4160 Volt motor switch-gear, motor control centers, panel boards, control panels, etc., are grounded by direct connections,to the copper ground bus in-l stalled in the station. '440 Volt motors have j yp ground cables in the conduit feeding them.' This ground cable is connected to the motor frame I
or conduit box at one end, and the ground hus and the motor control center or switch-gear -
at the othe r end.
The driven ground rods that make upithe grid.
patterns are 5/8" copper clad rodsj each 30!
- s long.
Interconnecting-cables are 1000 acm (continued) e
.,*s.
4
..m
.._ 7
~
5/.;.
1 *.
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^
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Results of Visits (continued) x i
j r
tinned copper as are the ground grid risers j
to connect to-the ground' system.
A11~ con-i
- nections to the ground' rods ar a thermit welded, i
e ff..
and are accessible at' grado elevation-for testing -
.)
'the ground system.
~
T i
The test instrument is manufactured by the Biddle company and is-designed specifically for measuring the resistance to ground of l
ground connections.
The test uses driven j
-+
auxiliary reference" grounds.
The procedure l
states that the ground resistance of a system such as-the one installed should be 1 ohm'or less.
t In Amendment No. 11 to the FSAR, JC has described f
i the scope of the preoperational tests in considerabl.e detail.
l
(
Since this now becomes part of the license application,it
- j is planned to review the detailed test procedures again to insure that they comply with the application.
The inspector notes that the following items in the preoperational program' require further study:
+
1 i
i l.
No ultrasonic testing is planned on any. field welds on the primary system.
t-l T
2.
A repeat of the hydro test on the primary system j
may or may'not be planned.after the repair to i
the leaking control rod thimble.
3.
No efficiency. tests are planned on the absolute
~
filters as finally installed in the reactor.
4 building gas treatment system, 1;.
j i.
(continued)
)
i v4-
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i j
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Results of Visits (continued)
I o
s3 4.
No efficiency tests are planned on the charcoal filters as finally installed in the reactor building gas treatment system.
'5.
It is pisnned to time the scram.te'sts of each f4
'~
rod thrice.
A more statistically significant' y
i program, which might forestall' future problems, would test one rod 50 -times, a second 25, a _ third 12, a fcurth 6, and the rest three each.
e 6.
If a full dummy core is not available, is it-possible to scram 136 rods at the same time?
7.
The presently planned emergency core cooling l
preoperational test does not' demonstrate all possible modes of failures of water and electrical?
sources, and how these failures can be coped with.
j 8.
No quantitative evaluation of the discharge.from each nozzle is planned in the containment spray test.
Air will be blown through the nozzles, 4
but individual flows will not be measured.
t t
9.
The preoperational tests which the inspector has seen do not describe-on-site fuel element in-spection before loading.
if ff 10.
All piping from the torus to the suction side of the core spray pumps has had only visual in-l l
spection and no further,. inspection is planned.
[
y 11.
The control room switch for operation of the i
relief valves is not 'a dead-man switch.,,, '
4 1
12.
Thetotalizerforcontainmentsumpgallonaheis mounted on the rear of the main control panel.
I (continued) x 4
4 s-w5.
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- E j-Results of Visits '(continued) j i
- s bi 13.
There is no lock on the local auto-manual switch
}h at the hydraulic drive for the recirculation pumps.
14.
The accesswways, where a torus breach could flood 4
out the core spray pumps,.have not been dammed.
.mg rr 15.
There is no separating partition between the two
)
battery banks of the station battery.
16.
It is not clear that there is complete separation j
of all elements of the two diesel generator system.
]
17.
The two relays in each channel of the protection system in the control room are not separated by a physical barrier.
18.
It is not planned to check the sampling systen or the calibration of the stack gas monitor
?
prior to loading.
JC intends using the manu-facturer's data and check this after operation of grab samples.
l 19.
It is not planned to test the primary system i
relief valves on-site, although JC personnel have expressed interest in the Crosby Lift device which the inspector described as being used at Connecticut Yankee Atomic Power Company.
44t:
20.
The effect of loss of air pressure to,the turbine pressure regulator system needs further study.
21.
The inspector has discussed with Mr. Hess the need for locating the atmospheric tap during the reactor building leak rate ' test in such a l
location that wind effects are minimized.
The exact location should be checked.
l (continued) o
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+
(continued) l Results of Visits
' I T
The inspector discussed the preoperational test i
' program with Messrs. Hetrick and Hess, and described-the t -
items noted above on which the ' inspector still had questions.
They were noncommittal in. reply, saying that they would look
,.g l further into these items.
The inspector pointed ~out that,
' ' ~ j as the proposed preoperational test program'is studied in' y
further detail,.there may be more questions to;be' asked and these questions would be brought up to JC and GE as soon as they were unearthed. Mr. Hess stated that GE intended completing all the tests in the two volumes of j
preoperational test procedures prior to -loading, with certain exceptions.
GE would prefer doing the following te sts after loading:
1.
Containment leak rate test.
GE's argument'is that-the dry well head would have to be put on
, i for the test and-off again after loading..
Furthermore, the dry well' head is necessarily off during loading.
. 1 2.
The radioactive waste building, as noted above under paragraph II.B.,
Plant Status, is months behind schedule. -GE wants to checkout-each sub-system of the radioactive waste system as -its.
construction is completed.- Mr. Hess pointed-out that, in case of-a contamination incident during loading or early operation, tank storage,-
l7 already installed, is available for holdup.
4 I
Liquid wastes could then be-retained'in bulk j
until the treatment facility is constructed and ready for operation.
The: inspector replied that while reasonable men may agree
)
.l-that the probability of a guillotine' break j
of a recirculation line is vanishingly '
q small, there have been many incidents in-volving radioactive releases in radioactive.
4 waste facilities at water reactors.
(continued)
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Results of Visits -(continued)
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- and controls would be installed as originally.
j 3.
The second diesel generator may not.be_in-stalled when loading is planned.
Wiring-j
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g.f' planned for a single diesel, and changed.when
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. the second unit is. installed.
'4.
Turbine controls will not be completely checked out since sufficient steam will not be' available to roll the turbine.
Mr. Hess~ stated that at Big Rock and at the Japanese.JPDR, the turbines were first rolled and controls checked out with nuclear steam.
He said that they will stroke!
valves '- the overspeed governor, and the bypass before loading.
l
+
5.
The expansion tests will not be completed before loading. Preliminary settings will be made prior i
to, and during recirculation' loop operation, but' t
final adjustments will be made after nuclear steam is available.
j 6.
GE wants to defer the hot runs of the recirculation pumps until after loading.
The '. loops would be run cold as a preliminary check before loading.
1 t
J l
Mr. Hess'. argument is that the pumps sh k id only be operated at full speed at rated temperatures which may not be fully attainable with pump d@
heat, and he said that the accelerometers to' be-installod in the reactor vessel are tempera-ture sensitive.
They might be damaged by a' hot run before loading.
The inspector pointed out that subsequent problems, which a' full heatup might uncover,-might require-anlunloading of the core.
Mr. Hess replied that that is the risk'they would take.
4 9
(continued)
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'P The inspector advised Mr..Hess to write a ' detailed proposal to Jersey Central on ' exactly what GE wasld do and ch what it would not do prior to loading to make 'sure that' everyone" involved, including the inspector, completely bj understood the proposed program.- Mr. Hess agreed to do;
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this, and the inspector said that he would report immediaitely
}'
to hisJsuperiors in the Commission the proposed exceptions to hasten an official reply.
4 4
N.
Interview with Management 1
On September 22, 1967, the inspector had a five hour meeting with Mr. George Ritter, Vice President, JC.
The meeting was held. at the new offices of the Nuclear-Power Group of the General Public Utilities Corporation in Parsippany, New Jersey.
On previous occasions, the i
inspector has expressed concern for the long-range.
company plans for Messrs. Hetrick and Finfrock.
These l
i men are not direct-employees of JC; they work for s
Metropolitan Edison and Pennsylvania Electric.
They are-the two key people at Oyster Creek.
They are the only-l engineers at the plant with considerable training and 11
[
experience in the nuclear power field.
one would' expect
)
that it is their hope to graduate from plant operation to a project engineering office job.
As a matter of fact, Mr. Finfrock is not resident at the site and spends about three days a week at the plant.
Mr. McCluskey has told the p
inspector - and this has been reported in a' previous: in--
management to hize or train replacements for these men-if it' spection report - that for two years he has pressed his i
is not planned that they stay.
Mr. Ritter said that1he is well aware of the problem and the concern and that he.has a firm commitment from Mr. William Kuhn, the President
^
of General Public Utiliti4s; that these two men will stay J
at oyster Creek as long as they are needed.
This was-i defined by Mr. Ritter as possibly a year for Mr. Finfrock l'
and three years for Mr. Hetrick.
The inspector observes that, a
in showing the inspector through the new office space, Mr.
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Ritter pointed out desks for both men.
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l Results of Visits -(continued);
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J a-I Mr. Ritter -said that he would apprecinte it,1f the l'
following information is kept confidential _and not.made known to the men at the plant.
He said that.he is considering j
Mr. Doyle, the Chemical Supervisor, as a replacement for Mr.
4 Finfrock and Mr. Agon as a replacement.for Me. Hetrick.
The.
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FSAR has - resumes for both Messrs. Agon and Sullivan, the' two -
[-
Assistant Technical Engineers.
Mr. Ritter said that he con-~
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- sidered'Mr. Sullivan to be more inclined towards' analytical work, while' Mr. ~ Agon was more of the operator type.
While discussing personalities, Mr. Ritter' declared l
that he was well aware that Mr. Don Reese does not always!
project a favorable image.
In his zeal to accommodate,.
Mr. Reese'sometimes attempts to answer.before he completely _.
understands the' question.
Mr. Ritter said that Mr.. Reese.
himself is aware of-this shortcoming, but that back in the 1
office,.Mr. Reese'is a very competent engineer.
The inspector inquired whether,:in hoping to groom i
Mr. Agon for a more responsible position, Mr. Ritter has
]
~
considered assigning the internal-audit function to him.
Mr. Agon would then be responsible for such things as check,
1 ing logs on a regular' basis, and for regular' and unannounced j
g tours to see that the operators.are following. the prescribed procedures.
Mr. -Ritter. stated that he is hesitant-to assign this role to Mr. Agon since.Mr. Agon is relatively new both-to the field and to the plant, and Mr. Ritter does not want q7Ipf to reveal his plans.for Mr. Agon for fear of ' generating :
dissension on the staff.
The inspector pointed out that
. [
. in the present organization, there are no plans for. audit outside of the line organization.- Mr. Ritter replied =that in conventional plants, the heart of good' operation is -that "every man knows his job"- and that there is good verbal' communication at shift turnover.
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. j; Results of-Visits (continued) r
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The inspector said that this reactor is orders of
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magnitude more complex, and the consequences of an accident l
orders more severe, than a conventional plant..Thus,.in f
the operating system there must be close control over the y 4" operators rather than the fervent hope that "each man l
knows his job".
It follows that, in a power reacts, the..
I.
heart of good operation lies in strict adherence to detailed.
l written operating procedures.
Mr. Ritter replied'that he realhes the necessity for operating.via procedure' an'd that -
such procedures are being developed now by plant pe rsonnel..
]
The inspector described to Mr. Ritter what is an.
I emergency operating procedure.
The concept was new to Mr.
+
Ritter. One starts with simple and more or less predictable equipment malfunctions. The inspector.said that in ca: well-managed organization, such procedures are in regular andl
?
constant develcpment and review. ~As long as one can invent' j'
an inc'ident arising out of an operator error or an equipment failure or any combination thereof, then this situation should be covered by a written procedure.
The real situation may never occur in the life of the plant; how.
D j
ever, the generation of such procedures, and the learning j.
of them by operators, is an excellent training device.
Mr.
j
?
Ritter replied that there can be an infinite number of I
combinations of things going wrong.
The_' inspector agreed j
l and stated that that is precisely why one must continue to
.j
'I-study the plant over its life time.
Incidents seldom j
4gi.7 occur in a predictable sequence...Is it not then. pre-ferable to attempt to plan for all contingencies, rather than to pray that when the strange combination of events does occur, the operator "knows his job". -As a final sales point, the inspector stated that the generation of pro-y cedures requires thought, not money.,
The inspector stated that, owing to the turakey nature of this project, there has been relatively2little serveillance by JC of exactly what they have bought and how (continued) 1
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i Results of Visits (continued) i y
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t it is put together. ~ The only way at this point that JC could Wure that they are getting their money's worth, is from a thorough preoperational test program.
Mr. Ritter d
stated that he agreed on the importance of the preoperational l
tests and that the whole program would be completed.
At the f*
time of this interview, the inspector had.not been approached l
[
by GE for exception to completion of any items in the pre-operational test program before loading.
Mr. Ritter explained the General Public Utilities Nuclear Power Group organization.
Mr. Louis Roddis is the group leader.
His principal office will be in New York.
Mr. Ritter said that he planned to assemble the following Deople at the Parsippany Offices Mr. Reese - He will be Project Manager on the Three Mile Project Mr. Finfrock Mr. Hetrick Mr. Neeley - He has attended DRL meetings on Oyster
~
'~
Creek and was a Project Manager with Allis-Chalmers.
Mr. Layman All from Saxton Nuclear. Experimental l
Mr. Beerman Mr. Montgomery Corporation i
Mr. Ritter also brought with him his mechanical he engineering group from JC.
He made no claim that this wa's j
a nuclear engineering group.
He said these people were skilled in hydro power projects and structural engineering.
In describing the organization, Mr. Ritter stated that Mr. McCluskey, the Oyster Creek Plant Superintendent, reports to Mr. George Kelcec, Manager of Generation Stations.
Mr. Ritter did not claim that Mr. Kelcec had any knowledge (continued) l
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, 3 zw jy Results of Visits (continued) j l
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.Mr. Ritter said 1
3 or experience in the nuclear power. field.
that'in-the-old~line JC. organization,.for quite a while,
.l he was the only professional engineer..His superiors j
B
.in the organization were from other, disciplines.
There l
j
,4 pW xl was originally an electric distribution group but,no mechanical engineering group.
If the company had an -
)
engineering problem, it employed outside _ engineering firms j
and consultants.
United Engineers,and Pickard and Lowe have l
t been used on a number of' occasions.
Mr. Ritter said that for j
f.
Oyster Creek, the same kind of program is' planned. If a l
particular problem arises requiring talents not in their-l own organization, they'll hire outside consultants.
[
The inspector inquired of their plans for outside-
'l audit of the whole administration of oyster Creek, including-l both operation and engineering.
Mr. Ritter replied as he j
did before, that if the need arose, they would hire outside I
i consultants.
The inspector-pointed.out that they, being
- d' so close to the problem, may not realize when they need-
- [
help.
One of the virtues of having an outside consultant; l}
come in is to look-at the overall picture and he may
- j i
unearth problems that one's own operating and engineeringL
, groups haven't seen.
The inspector declared that it has f
'^ been his observation that,'in plants with good morale and j
good communication, the internal plant safety committee-j appears to be in almost continual session.
When a problem comes up, the group gets together on a' moment's notice.
j h.
However, many organizations are weak >in the area of outside I
audit Innd review.
The inspector advised Mr. Ritter that l
the whole field of organization, procedure and audit would
[
be' subject for further questioning by DRL before the operating.
]
license is issued and suggested that'Mr. Ritter-gite more.
l
>g h'
thought to the topic.
Questions are certainly going to' l
be asked on the function and methods of the offsite Safety
[
Review Committee.
j; j
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(continued) i e
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Results of Visits -(continued)
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- Q~L The inspector' emphasized the need for good. records
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during the preoperational test program for two reasons:
1.~
Jc can feel confident that the machine they I
are buying has been adequately demonstrated.
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-It eases the job of.the compliance inspector l
j l
who must attest that the plant.has been;,
j completely checked out.
With many' tests, the test may proceed up to a certain. point and then something happens to delay further progress, usually because of some an1 function of equip-ment.
The test is then left half finished.
Without decent record keeping, the result is
.j chaos.
When tho' test is taken up again,
~
one doesn't know exactly where.to begin. The q
test is seldom started,over'from scratch..
l A
g-guestimate is made.on whereito resume,'andiin i
3 j
this process a vital component may be over-
~ looked and never get checked out..It would l
j
-be prudent to ' assign record keeping to one man.
He need not be responsible for signing off'on f
the adequacy of~a test or the' evaluation of test results. - he would simply keep complate' records, and remind.those responsible-for" j
j i
sign off and evaluation of any discrepancies..
- 'j Mr. Hetrick is presently reviewing and approving.
l I'
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test procedures,: but.is also very busy with.
j gde operatins procedures'. ~ Mr. Ritter agreed that y.
he could use help in this program.'
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