ML20107C870
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To:
. James P. 'O'Reilly Directorate of Regulatory Operations
%gion 1 631 Park Avenue King of, Prussia, Pennsylvanin 19406 i
From:
Jersey Central Power 5 Light Company oyster Creek Nuclear Generating Station Docket #50-219
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Forked River, New Jersey 08731 f
Subject :
' Abnormal Occurrence Report No. 50 219/74/ 1 The following is a preliminary report being submitted in compliance with the Technical Specifications paragraph 6.6.2.
Prclininary Approval:
h/
A11M 2/19/74
. T. Carroll, JM D
cc Mr. A. Giambusso 1
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, Report Dateg 2/19/74 Occurrence:
1500 l:
0 OYSTER CREEK NUCI,UAR UUNERATING STATION i
' PORKED RIVER, NIN JERSEY 08731 Abnormal Occurrence Report No. S0 219/74/11 Violat' ion of the.Technkcal Specifications, paragraph N/A,
IDDUIFICATION 0F OCCURRENCE:
Failure of four torus to drywe11 vacuuta breakern to demm-strate operability during' weekly surveillarice testing.
l 1his event la considerfd to be an abnormat occurrence as de-fined in the Tedinical Specifications, paragraph _
1.15B CONDITIONS PRIOR To OCCURRENCE:
X Steady State Power Routine Shutdown Hot Standby
_ Operation Cold Shutdown
. Load Changes During Refueling Shutdown Routino Power Operation Routine Startup other (Specify)
_ Operation The major plant parameters at the tino of the event were as follows:
Power: Core, 1904 !Mt Elec., 670 )Me Flow! Hecire,, 15,5 x 10" ppm Food., 7.23 x 10'.Ib/hr Stack Gas: 29,000 DCi/sec DESCRIPTION'
' On Friday, February 15, 1974 at approximately 1500, while per-OF OCCURRENCE:
fortning weekly surveillance te.e, ting on the fourteen tonis to drywcIl vacuts breakers, it was found that four of the vacuum breakers (V-26-5, 6, 9, and 11) fni ted to demonstrate operabili ty, This surveillance testing was being performed to satisfy the requirements of AEC letter (D. J. Skovholt to R,11, Site, dated January 30,1974)~, This operability testing basically consisted of manually opening each valve to the fully open position 3Dd i
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.t kep;rt NA 50-219/74/11 Page 2 then allowing it to close without assistance. Any hanging up in '_.s 7pening or closing motirms was. interpreted as non oper-
- ability, Valve V 26 5 was side operabic imacdiately with the application of several successive opening and closing movements.
Plant operation continued on the basis of the requirements of paragraph B.h of the. referenced letter, which allows i;ontinued operation if not more thati 2% of t.hese vacuum breakerr, nre in-operable.
Maintenance on the-remaining three inoperable vacuum breakers (V-26-6, 9, and 11) was complete at approximately 0100 on February 16, 1974.
APPAkENT CAUSB Design Proceduro j
OF OCCURRENCE:
Manufacturc X_
UnuFuel SorVice Condition Installation /
Inc. Environmental const ruction Coleponent Psilure
_ Operator
_,; 0ther (Specify)
It 'is believod that these failures were the result of valve packing glands being adjusted too tightly. This condition may have been caused or aE2ravated by the low pressure, high hum.
idity environment in which the valves operate. A 81tallar failure was reported as Abnormal Occurrence Report. No. 73-2, dated January 6,1973, ANALYSIS OF The drywell-torus vacuum breaker system is required to prevent OCCURRENCD:
water osc111ation in the downconers due to low steam flow rates in the downcomers and t.o provide protection against negative pressure conditions in the containment vessel. De significance
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R: port Ho, 50-219/74/11_
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of this event ~1s 'that for a peklod of time plant operation con-tinued with four vacuts breakers. inoperable. Plant operation may continue with a maximum of three inoperable vacuum breakers, as per paragraph B.S of AsC' letter (D. J. Skovholt to R. H. $1ms, dated January 30,1974). Additionally, the besos of the Technical Specifications state that this condition has no deliterious effect on negative pressure protection since only about 25% of the available vactaus relief capacity is required for this protection.
CORRl!Cr1VD Valves V 26 5, 6, and 11 were freed with repetitive opening ACTION:
and closing movements, Valve V-26-9 required packing adjust-
- nent, The results of future weckly stm'cilience testing on these valves will be closely monitored, Further corrective action j
will be dictated by the results of this testing, i
. FAILURE DATA:
Basic valve data are as follows:
Manufacturer - Atwood 6 Morrill Type - ButterOy Vent Area - 1.75 square foot per velvo Prepared by:
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Date:
2/19/74 l
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O Jersey Central Power & Light Company f v
MADISON AVENUE AT PUNCH BOWL ROAD
- MORRISTOWN, N.J. 07960
- 201-539-6111 useum or rus gy*] Public Utilities Corporation General SYSTEN February 19, 1974 Mr. A. Giambusso Deputy Director for Reactor Projects Directorate of Licensing United States Atomic Energy Commission Washington, D. C. 20545
Dear Mr. Giambusso:
Subject:
Oyster Creek Station Docket No. 50-219 Hydraulic Shock and Sway Arrestor Inspection - January 1974 The purpose of this letter is to forward to you a report of an inspection conducted on the hydraulic shock and sway ~ arrestors (snubbers) located in the drywell at the Oyster Creek Station during the January 1974 shutdown.
The report is responsive to the inspection and reporting require-4 ments of Directorate of Licensing letter (Donald J. Skovholt to Jersey Central Power 6 Light Company) dated October 1, 1973.
During the plant shutdown which began on January 12, 1974, a total of 90 (65 Bergen Patterson and 25 Grinnel) snubbers were inspected. Thirty units were
. nlaced for the various reasons given in the attached report.
Replace-ments were made with snubbers rebuilt with complete ethylene propylene seal kits.
The surveillance program outlined in my letter of December 7,1973 will be continued until a satisfactory solution to the snubber problem has been found.
Enclosed are forty copies of this submittal.
l
. Very truly yours, 1
W& ' '
Donald A. Ross Md</AM 69 Manager, Nuclear Generating stations Enclosures cc: Mr. J. P. O'Reilly, Director Directorate of Regulatory Operations, Region 1 Mr. D. J. Skovholt.
'""#*y Assistant Director for Operating Reactors i
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. JERSEY CENTRAL POWER 4.LIGiff COMPANY OYSTER CREEK NOCLEAR GENERATING STATION DRYWELL SNUBBER ACTIVITIES JANUAkY'1974 l
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4 On January 12, 1974, after achieving the 40-hour stay time access requirement, an inspection of the hydraulic shock and sway arrestors in the drywell was initiated. All units, which included 65 Bergen-Paterson and 25 Grinnell snubbers, were inspected thoroughly and those units un-able to meet the rod freedom, fluid Icvel or no visible leakage require-ments were tagged for removal. Replacements were made with snubbers rebuilt with the complete ethylene propylene seal kits.
Alemite fittings with EP inserts were used on all the rebuilt units which insures that all sealing material is of the recommended type.
The inspection of the Bergen-Paterson snubbers located five failed units and one leaking unit which, though still operable, had a low oil level. These snubbers were tagged for removal as " failed" to segregate them from other units to be removed.
Five leaking snubbers with sufficient fluid IcVels were also tagged for removal. Of the units tagged " failed,"
a visual inspection of the seals revealed that some of the seals did deteriorate to a point of failure while others looked in excellent condi-tion. There seemed to be several types of material used in each unit, and to determine which material failed and the degree of the deterioration of the remaining seals, an analysis using infared scans and microscopic examination is being conducted by the GPU Laboratory.
A supplementary report of the test results will be generated upon their receipt.
During the inspection of the seals, it was determined that two of the failed units had no rebuilding documentation available.
Further in-vestigation revealed a total of nine undocumented snubbers from the Septenber rebuilding activities. To insure an accurate record of the material used in the drywell, these nine snubbers were also replaced with rebuilt units.
A review of the information obtained from the inspection showed that four of the failed units were located above the biological shield. There were also two undocumented units at that elevation and it was decided at that time to replace all the hydraulic snubbers in that area as a i
preventive measure to insure units containing all ethylene propylene seal material in the area of the drywell having the worst environmental condi-i
- tions, in addition to the above requirements for removal, twelve old series snubbers had been designated for replacement prior to the inspection.
These units were of the type which could not be fully rebuilt with the full EP kits, These snubbers were tagged regardless of their condition;
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however, their condition was recorded on the as found sheets.
A total of 30 Bergen-Paterson hydraulic shock and sway arrestors have been replaced in the drywell during the shutdown. Of the 30 units,
some fell into more than one category.
Table 1 of this report lists all the snubbers that were replaced and the reason (s) for removal.
Table II lists the installed units and corresponds with Table 1.
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Inspection of the Grinnell snubbers, located on the recirculation l
i pumps, yielded two units which had very little. oil in.their accumulator and seven with reservoirs less than one-third filled. The remaining sixteen were in satisfactory condition. The nine units with low fluid levels had their accumulators refilled and one of the two relatively-empty units had the coupling between the accumulator and piston housing tightened. The as found and as left conditions are listed at the end of the report.
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TABLE 1 SNUBBERS REPLACED DURING JANUARY 1974 OLTTAGE 487574 North Main Steam 23' No documentation 487557-North Main Steam 51' No documentation 487395 North Main Steam 51' No documentation
'487538 North Main Steam 60' Leaking S-Tube 487499.
North Feedwater 23' No documentation 487491 North Feedwater 51' No documentation 487561 South Main Steam 23' No documentation 469862.
South Main Steam 60 ' -
Old series snubber
~487573-South Feedwater 23' Failed (leaking)
No documentation 477177 South Feedwater 51' Old series snubber 487517 North Emergency Cond.
Condensate Return 75' Failed
-470924-North. Emergency Cond.
Condensate Return 95' Failed Old series snubber 487492-North Emergency Cond.
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Condens ate. Return 95' Preventive Action 487510 North Emergency Cond.
Steam,Line 95' Preventive Action 487487 North Emergency Cond.
Condensate Return 95' Failed 487447 South Emergency Cond.
Condensate Return 95' Leaking 487502 South Emergency Cond.
Condensate Return 95' No documentation Preventive Action 487494 South Emergency Cond.
Steam Line 95' Preventive Action 469962 South Emergency Cond.
Steam Line 95' Failed Old series snubber 487549 North Core Spray 75' Leaking 487552 South Core Spray 95' No documentation Preventive Action 487356 South Core Spray 95' Preventive. Action
-477376 South Core Spray 95' Failed Old series snubber r
Preventive Action i
469860 South Elcetsmatic Relief 51' Old series snubber 477288' Cleanup System 55' Old series snubber l
469852 Cleanup System 65' Old series snubber 469902-
_ Shutdown ~ Cooling 48' Old series snubber 469900 Shutdown Cooling 48' Old series snubber 469901 Shutdown Cooling 51' Old series' snubber f
469939 Containment Spray 65' Old series snubber F
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' SNUBDERS INSTALLED DURING JANUARY 1974 OLTTAGE 487521 North Main Steam 23' F93501 #5 North Main Steam 51' F93501 #4 North Main Steam 51' 487487 North Main Steam 60' 487576 North Feedwater'-
23' 487517 North Feedwater.
51' F84806-3 South Main Steam 23' F95501 #2 South Main Steam 60' 487399 South Feedwater 23' 487549 South Feedwater 51' F93502 #2 N.. Condensate Ret.
75' 487561 N. Condensate Ret.
95' 487531-N. Condensate Ret.
958 F93501.#3 N. Condensate Ret.
95' 487499 N. Emergency Cond.
Steam Line 95' 487574 S. Condensate Ret.
95' 487502-S. Condensate Ret.
95' 487494 S. Emergency Cond.
Steam Line 95' F95222-2 S. Emergency Cond.
Steam Line 95' 4874--
North Core Spray 75' 487552 South Core Spray.
90' 487557 South Core Spray 95' F93502 #1 South Core Spray 95' 487446 S. Electromatic Relief 51'
-487495 Cleanup System 55' 487516 Cleanup System 65' 487404 Shutdown Cooling 48' 487528 Shutdown Cooling 48' 487573 Shutdown Cooling 51' F93501 #1 Containment Spray 65' 4
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GRINNEL SNUBBERS - CONDITION AS FOUND il A - Recirculation Pump B - Recirculation Pump A - 1/4 A - 3/4 B-1 B - 1/2 C - 1/8
. C - 0 oil on floor i
D.- 1/3 D-1 E-1 E - 1/8 C - Recirculation Pump D - Recirculation Pump
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GRINNEL SNUBBERS - CONDITION AS LEFT f
A - Recirculation Pump B - Recirculation Pump A-1 A - 3/4 i
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0 = Empty Accumulator 1 = Full Accumulator a
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