ML20108D507
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i ENCLOSURE Description of Violations Jersey Central Power and Light Company Horristown, New Jersey 07960
,g g Edgi Deckat No. 50-219
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License No. DPR-16 Certain activities under your license appear to be in violation of AEC regulations and license requirements. These apparent violations are considered to be of Category II severity.
1.
Technical Specification 4.5 refers to containment system leakage rates. Section 4.5F.1(d) provides a limit for "any one penetration or isolation valve 5% Leo (20)."
Contrary to this requirement main steam' isolation valves failed to meet allowable leakage requirements as follows:
NS035 on September 9, 1973 with measured leakage in a.
excess of 100 SCFH.
(JCP&L letters to DL dated September 21, 1973 and December 7, 1973 (Revised))
b.
NSO4A and B on September 27, 1973 with measured leakage of 96.59 and 15.15 SCFH respectively.
(JCP&L letter to DL dated October 12, 1973) c.
NSO4A on January 16, 1974 with measured leakage of 31.7 SCFH.
(JCP&L letter to DL dated January 25, 1974) i 2.
Technical Specification 2.3.(1)s "APRM" states in part the limiting safety system setting shall be as follows:
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"For recirculation flow, W161x10 lb/hr
<((1.12x10-6) W+51.76) percent of rated neutron flux l
for total peaking factors 13.01 3*01
<((1.12x10-6) W+51.76) (b)e,ercent of rated neutron p
flux for total peaking f r
PF>3.01."
Further Technical Specification 2.3(2)s "APRM Control Rod Block" states in part, i
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a 0 lb/hrt "For recirculation flow, Q61x10
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Qi 3((1.12x10-0) M37.72) percent of rated neutron flux for
{i total peaking factors 33.03 f((1.12x10-6) W37.72) (3.03 ) percent of rated neutron flux fortotalpeakingfactor,hF>3.03."
l Contrary to this requirement, on October 6,1973, with a recirculation flow of 30x106 lbs/hr, APRMS were set such that 100% of the APRMS corresponded to 1400 MW(t), accounting for jl peaking factors of 4.15 which resulted in a setting less non-servative than specified above.
(JCP&L letter to DL dated October 16,1973) 1 j
3.
Technical specification 2.3.7 states, the limiting safety system setting for the low pressure main steen line MSIY
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closure shall be "> 850 peig."
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Contrary to this requirenent during surveillance, trips failed to occur at the required set point setting as follows:
4 RE 23&, B, C and D (JCP&L letter to DL dated December a.
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24,1973) b.
RE 23C (JCP&L letter to DL dated January 15,1974) j We note that your ongoing audit and review has disclosed that a head correction factor had not been applied such that these switches have been set in violation of the Technical Specifications since initial startsp.
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4.
Technical specification Tabla 3.1.1 specifies protective l
instrumentation requirements. Section 3.1.1.B.6 provides settings for high radiation in main steen tunnel as follows:
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"$10K Normal background."
Contrary to this requirement, on December 27, 1973 Monitor No. RN05& failed to trip when tested.
(JCP&L letter i
to DL dated January 9, 1974)
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5.
Technical Specification 3.5. A 6 s tates in part...........
"the primary contalment atmosphere shall be reduced to y
less than 5.0% 02 with nitrogen gas.within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after 4
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the reactor mode selector switch is placed in the run mode."
contrary to this requirement, at 10:00 A.M. January 22, 1974 the torus atmosphere contained 6.2% 02 and the mode switch had been placed in run at 10:00 A.M. January 21, 1974.
(JCP&L letter to DL dated January 26,1974) 6.
Technical Specification 2.3.5 " Reactor High Pressure, Isolation condenser Initistfon". states the limiting safety system setting shall be "31060 peig with time delay
$ 15 seconds.
Contrary to this requirement on January 17, 1974 during testing three time delay relays failed to close within the 15 second limit.
(JCP&L letter to DL dated January 29,1974) 7.
Technical Specification 4.7.A.6 states "The diesel generators' starting batteries shall be tested and monitored the same as the station batteries Technical Specification 4.7.B."
Section 4.7.B.1 states in part, "The specific gravity and voltage......
the temperature......and the overall battery voltage shall be N
measured weekly."
Contrary to this requirement, tests performed at the interval May 10, 21, and June 8, 1973, did not constitute a weekly frequency.
j 8.
Technical Specification 6.2.A states " Detailed written procedures with appropriate checkoff lists and instructions shall be provided for the following conditions:"
Technical Specification 6.2.A.4 references " Preventive or corrective maintenance operations which could have an effect on the safety of the reactor."
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Contrary to this requirement on December 13, 1973, jumpers were improperly installed, resulting in a loss of 125V DC power supplying instrtsnentation to safeguards systems. The referenced operation was conducted without a procedure.
It is noted that a procedure was subsequently written and approved by PORC.
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The following apparent violation is considered to be of Category III severity.
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Paragraph 6.6.2 of the Technical Specifications requires that
'you notify the Director of the Regional Regulatory Operations i
office within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone and telegraph followed by a written report within 10 days to the Director of Licensing.
Contrary to the above, the following abnormal occurence was not reported within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, as required:
Abnormal occurrence 73-23(1) dated September 25, 1973.
Further,10 day reports for the following abnormal occurrences were not submitted within the specified intervals (1) A0 73-22 (10 day report) dated September 21, 1973 (2) A0 73-24 (10 day report) dated October 12, 1973 i
(3) A0 73-32 (10 day report) dated January 7, 1974 (4) A0 73-34 (10 day report) dated January 9, 1974
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- OFFICS
.-n DAT4 Form ALC 318 (Rev 9-53) AECM 0240
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J op James P. O'Reilly To:
Directorate of Regulatory operations Region I f<_
631 Park Avenue King of Prussia, Pennsylvania
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Jersey Central Power 4 Light Company Prom.
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Oyster Creek Nuclear Generating Station Docket #50-219 Porked River, New Jersey 08731
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Subject:
. Abnormal Occurrence Report No. 50-219/74/ &
,J 1he following is a preliminary report being submitted in compliance with the Technical Specifications parsgraph 6.6.2.
Preliminaiy Approval:
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I" Abnormal Occurrence I
Report No. 50-219/74/ $6 1t i I:.
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IDENTIFICATION Vioistion of the Tedinical Specifications, paragraph N/g_,
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1his event is considered to be an abnormal occurrence as de-
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fined in the Technical Specifications, paragraph 145 b GB(DITIONS PRIOR ii*
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APR 111974 4
Jersey Centrol Power and Light Ceapany Doeket No. 50-219 Attenties: Mr. Ivan Fiafreek Lisease No. DPR-16 i
Vice President of Poeer Generation 1
Madises Avteus at Punebbowl Reed Morristown, New Jersey 07960 Referesse t Your letter dated )threb 13, 1974 In response to our letter dated February 11, 1974 Centlemen:
Thank you for informing us of the corrective and preventive actione j
you doeusented in response to our correspondence. The information contained in your letter is being reviewed.
In the event that j
there are further questions regarding this information, we will 1
review them at our next inspection.
l Your cooperation with us is appreciated.
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Sincerely, 4
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James P. O'Reilly 1
Director i
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R0 Chief, FS&EB RO:HQ (4)
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PDR Local PDR NSIC DTIE State of New Jersey t
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Mann Knapp Nelson.
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