ML20087A632
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- %9" UNITED STATES ATOMIC ENERGY COM' ISSION M
DIVISION OF COMPLIANCE I. LICENSEE
- 2. REGIONAL OFFICE JERSEY CENTRAL POWER & LIGH't CO, U. S. ATOMIC ENERGY COMMISSION Madison Avenue at Punchbowl Road Morristown, New Jersey Region I, Division of Cosapliance 970 Broad Street Newark, New Jersey 07102
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Ye)"$ M I['10 12, 1969
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5 The following activities under your license (identified in Item No. 3 above) appear to be in noncompliance with AsC or license requirements, as indicated.
regulations Surveillance of the following instrumentation was not performed in cecordance with the requirements of section 4.1 of the technical opecifications:
The first calibration of the " low-low water level" channel since a.
initial critical operation (May 3,1969)~ was on August 22, 1969.
Item 4. of Table 4.1.1 of the technical specifications requires the " low-low water level" channel to be calibrated at least once
.i every three months.
b.
The first test of the " low-low-low water level" channel following initial criticality was performed on June 30, 1969.
Item 6. of Table 4.1.1 of the technical specifications requires the " low-low-low water level" channel to be tested at least once per month.
'The first calibrations of the "high radiation in reactor building-c.
operating floor" and "high radiation in reactor building-ventilation exhaust" monitor channels were performed on August 15 and August 22, 1969, respectively.
Also, the records.of weekly tests of one of the other of the above channels conducted during the periods of May 4 - 10, Ray 18 - 24, June 8 - 14 June 29 -
July 5, July 6 - 12, and July 20 - 26, 1969, could not be located.
Item 14. of Table 4.1.1 of the technical specifications requires the "high radiation in reactor building" monitoring channels to i
be calibrated at least once every three months and to be tested at least once per week 9500070097 950227 A
DEKOK95-36 PDR d.
At the time of the September 10 - 12 visit, the "high radiation j
on air ejector offsas" monitor channels had not yet been calibrated following initial criticality.
Further, the monitor Supphmentary page - attached.g
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ucast Page of Pages.
- 5. (Continued from Form AEC-592) channels were not reset to respond to the appropriate reading
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for the calibration source when tested on March 3, 1969.
specifically, the co-60 calibration source measured 1.12 R/hr at 3 feet but the two channels, when tested with the source at 3 feet, only read 1.0 R/hr and 0.8 R/hr.
There was no record of a weekly test of the off-gas monitors during the period of August 17 - 23, 1969.
Item 15. of Table 4.1.1 of the technical specifications requires the "high radiation on air ejector off-gae monitor channels to a
be calibrated at least once every three months and to be tested at least once per week.
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p 3944 October 24, 1969 J. P. O'Reilly,' Chief, Reactor Inspection & Enforcement Br.,
s Division of Compliance, Headquarters INQUIRY MEMORANDUM JERSEY CENTRAL POWER & LIGHT COMPANY (OYSTER CREEK 1), 219/69-H CONTROL ROD DRIVES CRUD PROBLEM - LICENSEE'S PROPOSED TESTING PROGRAM i
The following is a summary of the test program *JC-GE propose
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to conduct on their control rod drives subsequent to completion of the drive modifications (filter removals and changes) currently underway and prior to the resumption of their i
startup testing program.
It should be noted that it took considerable perseverance on the part of our inspector over the past week to get the licensee to define his program, and even then it was presented to us at "only preliminary thinking".
It should also be noted that this information came to us subsequent to the Skovholt contact with JC setting up the October 27, 1969 meeting.
A.
Cold Testing 1.
The following will be performed on each of the 137 drives g%
with the reactor at ambient temperature and unpressurized:
a.
Vent g
b.
Stroke and time - To accomplish proper adjustment l
of flow control valves.
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c.
Operate drive over several notches - to demonstrate proper timing.
d.
Scram time 2.
The reactor will then be pressurised to 1000 peig by means of the control rod drive pumps, and a selected O
eroup of 26 drives will be scram ti==d.
individum11y.
N COMPLIANCE omes,
CARL
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- Dhta i mi by.our...innpec. tor. in...;el.egan wit a
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T. McCluskey on October 23, L969.
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E.
Hot Testina (Hot Standby)
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1.
The same 26 selected in A.2. will be individually L
scram timed.
The accumulator charging line will be
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closed before testing each individual rod.
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Assuming no problems with the above, they would then continue i
to monitor the selected 26 drives during the resumed startup l
testing program.
Eight of the 137 drives will have inner filter i
screens installed (on outside of filter frame vs original in-l side), as part of a program by GE to determine the optimum size i
i filter screen.
These eight, summarized below, would be included in the selected 26.-
I No. Drives Size Mesh, Mils 1
1.2 (original)
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6 3
10 In response to an inquiry regarding the General Office Review Board (GORB) involvement in the current rod drive problem, McCluskey stated that they have reviewed the fix; however, i
he had not as yet decided if it was necessary that they review the above proposed test program.
1 R. T. Carlson Senior Reactor Inspector
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,f UNITED STATES h
ATOMIC ENERGY COMMISSION V
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WASHINGTON, D.C. 20545 J
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NOV 4 1969
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t D. J. Skovholt, Assistant Director i-for Reactor Operations g
Division,of Reactor Licensing (3) t JERSEY CENTRAL POJER AND LIGHI CalPANY (0YSTER CREEK) f DOCKET NO. 50-219 f
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f The enclosed report of c special inspection to investigate allega-I f.
tions made by Alan 11. Galer, a radio station news director, Asbury k
i Park, New Jersey, in connection)uith the subject facility is for-warded for information. These allegations were brought to the attention of Mr. L. D. Low by the Honorable William T. Cahill, Representative, Sixth Congressional District, New Jersey.
I safety significance at Oyster Creek' or any information of regula-f Our investigative efforts failed to develop neu information o#
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j tory interest not previously knosm to the regulatory staff.
This*
matter is considered to'be closed.
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l J. P. O'Reuy i
J. P. O'Reilly, Chief g
Reactor Inspection and Enforcement Branch l
Division of Compliance l
Enclosure:
Investigation Report
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cc w/ enclosure:
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- E. G. Case, DRS
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R. S. Boyd, DRL (2)
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4 S. Levine, DRL (6)
'j L. Kornblith, Jr., C0 1
i M T. Carlson, CD:1 w/o enci REG Central File i.
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