ML20087B033
Text
m
~
',y, g\\
?w k
4 p,._ p ~
n Jersey Central Powe & Light Cornpang~,,.I 4 y' M ADisoN AVENUE AT PUNCH BOWL Ro AD 9' MoRRISToWN, N.J. 07960 e 539 611I December 22, 1970 k>(E
~
, f it C J l
c i d, i.r-q l
Mr. Robert W. Kirkman, Director
-// : 4 United States Atomic Energy Commission
./
[,g %
Division of Compliance, Region I 4.3,-
170 Broad Street Newark, New Jersey 07102
[p
Dear Mr. Kirkman:
i This letter is in reply to your letter dated December 7, 1970 and attached Form AEC-592.
The paragraph numbers below correspond with those used on your Form AEC-592.
j_a.. No response is required in accordance with your letter a
referenced above.
An' analysis shoving the correct settings for 3
the isolation condenser flow instrumentation trips is included in 1
Amendment 60 to our License Application in answer to question 3b.
1 jb_. Diesel-generator 1-2 was not given a thorough annual inspection during 1969.
However, it was given a limited inspection when the engine of diesel-generator 1-1 was replaced in October of i
1969 A report of the inspection of diesel-generator 1-2 has been obtained from the manufacturer by telephone and is available for inspection'at the station. Both diesel-generator engines were inspected in accordance with the manufacturer's recommendations on November 12-13, 1970 and both generators were inspected in accordance with manufacturer's recommendations on November 16, 1970.
Reports of these inspections are also available at the station.
A procedure for these inspections has been formulated based on discussions with the manufacturer, and subsequent in-spections vill be made on an annual basis.
je. New check-off sheets for the surveillance requirements for the diesel-generator starting batteries have been completed and are in use.
They provide for documentation of the temperature reading of every fifth cell and the height of electrolyte.
These new check-off sheets were put into use on December 1, 1970.
i p
9500070279 950227 PDR FOIA DEKOK95-36 PDR l
o.
- t a
(J Mr. Robert W. Kirkman Page II December 22, 1970 i
2d. As noted in Se above, new check-off sheets have also been prepared for' the 125-volt station batteries that provide documentation of the temperature reading of every fifth cell and the height of electrolyte. These new check-off sheets were put into use on November 15, 1970.
le,. The standby gas treatment system, charcoal, and particulate e
filters were not tested for removal efficiency within the required i
six-month interval as the result of a scheduling error.
This error I
has been corrected, and the subject tests are now scheduled to be completed on a five-month interval; thus, allowing one month for contingencies. The charcoal filters, last tested on August 20, 1970, are now scheduled for retest in January 1971. The particulate filters, last tested on August 18, 1970, are also scheduled for retest in January 1971. A calendar has been set up to flag the-dates for future tests.
pf_. A careful review of all dryvell inerting events has been made, and this review has shown that at no time did the station fail to inert the dryvell with nitrogen within twenty-four hours after the reactor mode selector switch vag laced in the run mode. There has been; however[nimbeiofIric~idents hen the dryvell oxygen concen-
~
tration exceeded rive percent while the mode switch was in the run mode, and the plant was not shut down. It is our opinion that a reasonable time period should be allowed to correct an out-of-speci-fication condition and this was our interpretation of the Technical Specifications. However, such an allowance is not clearly stated for the inerting specification as it is for a number of other specifications. We plan to submit to the Commission a proposed change to this specification early in 1971 that will clarify this situation. In the meantime, the following actions have been taken to provide assurance that the specification vill be met:
- 1. Difficulties that were had with the operation of the oxygen analyzer were repaired on August 11, 1970; and since August 28, 1970, the analyzer has been calibrated weekly using a standard calibration gas.
Thus, ve are now able to carefully follow the oxygen concentra-tion and order additional nitrogen in sufficient time to prevent exceeding the five percent oxygen limit.
- 2. We have determined that the source of air leakage into the dryvell is from the instrument air pressure regulators for the main 8
i
A o
/
P ke jyjrt y, g,rkm
- Cember gg* 1970 1
the instrument aisteam isolation val ves, and we Our target r
date for the complsupply for theare proceeding with 1970 se etion of thisvalves to plans to a nitrogen convert conversion is Februar.
system 1
Very truly y
- yours, fn j
1-v v R. H. Sims y
pk Vice President I
l 1
i 1
i
)
i i
I i
i f
. *4
. yp:
f.
2 M
.3944 December 22, 1970 J. P. O'Reilly, Chief, Reactor Inspection & Enforcement Br.,
Division of Compliance, Headquarters INQUIRY MDIORANDUK NO. 219/70-K JERSEY CENTRAL POWER is LIGHT COMPANY (0YSTER tmerr 1)
FAILURg OF TORUS VACUUN BREAKERS The assigned inspector was contacted by Mr. J. Carroll, Operations Super-intendent on December 18, 1970 He conveyed the following information:
1.
Both torus vacuum breakers (butterfly valves) failed to operate during a surveillance test conducted on December 18, 1970. The reactor was operating at 1690 MWt at this time.
2.
Both vacutet breaker valves were reported to have been repaired within i
approximately 30 minutes. Following repairs, the valves were cycled four or five times and functioned normally.
3.
The problem with the valves was reported to be that the butterfly discs locked in the seats in the closed position and the air operators were unable to open the valves. One of the valves was found to have an in-properly adjusted linkage which resulted in the over-travel in the closed l
direction of the butterfly valve. The other valve was' reported to have a l
mis-adjustment on the butterfly stem (the other end.of the stee from l
which the operating linkage connects to) which caused the binding condition.
4.
JC intends to perform daily surveillance tests on both valves for the next several days. After confidence is established in valve performance, the testing frequency will be progressively increased back to the normal surveillance testing of once per month.
5.
JC intends to submit a written report to DRL within the 10 days required by the Technical Specifications.
6.
During the November, 1970 surveillance testing of these vacuum breakers, one of the vacuum breakers failed to open. This information was conveyed to the assigned inspector by Mr. T. McCluskey, Station superintendent.
He informed the inspector that the valves had functioned normally during a)1 previous surveillance tests and that it was not suspected that the.
~
particular failure could affect the other vacuum breaker. No Technical specifications were violated in the failure of a single vacuum breaker.and the licenser reporting requirements did not require that the licensee
/
I report this event.
I C0MPLIANCE McDERMOTTYmat "'CARLbON g9 7
sumaus >.2 2 2/70
~~
~
DATE>
Lg 6,i.'
W We are currently evaluating the noncompliance aspects of continued operation with both vacuum breaker valves inoperable for the 30-minute period. We will keep you advised of'any other significant information.
R. T. Carlson Senior Reactor Inspector cc:
E. G. Case, DRS (3)
F. A. Morris, DEL R. S. Boyd, DRL (2)
R. C. DeYoung, DEL (2)
D. J. Skovholt, DRL (3)
P. W. Inows, DEL (2)
A. Ciambusso, CO L. Kornblith, Jr., CO R. H. Engelken, CO Regional Directors, C0 REG Files
=
w 7-
.-p m