IR 05000219/1974013
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U.S. A'a0?lIC ENERGY C0m!ISSION
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DIRECTORATE OF REGU1ATORY OPERATIONS F#f
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REGION I
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- RO Inspec tion Report No:
50-219/74-13 Docket No:
50-219
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Licensee:
Jersey Central Power and Light: Company License No:
DPR-16 Madison Avenue at Punch Bowl Road Priority:
Morristown, New Jersey 07960
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Categorh~
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Locat' ion:
Oyster Creek Forked River, New Jersey
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1930 MWt, B' R (GE)
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Type of Licensee:
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Routine, unannounced Type of Inspection:
Dates of Inspection:
July 10-12, 1974 essi
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Dates of Previous Inspection:
June.6, 7, 17, 21, 22, 1974 Rsporting Inspector 2 (Y 3d/I7f
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Dad T.Rebelow[1,ReactorInspector Nuclear Support Section Accompanying Inspectors:
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Other Accompanying Personnel-Date
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Reviewed By:
C' O. k
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\\ Da te E. C. McCabe, Senior Reactor Inspector, Nuclear Support Sectio Reactor Operations Branch-9604170500 960213 PDR FOIA
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DEKOK95-258 PDR
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SUMHARY OF FINDINGS
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- jjj Enforcement Action y.qq
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A.
Violations 1.
In violation of Technical Specification Article 4.6.B.1.g the stack gas particulate filter was not analyzed for gross alpha, beta, and gamma activity within one week of removal. Licensee
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A0 50-219/74-24 refers.
(Details 3a)
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2.
In violation of Technical Specification Article 3.4.A.1, the
"B" Core Spray pump was unavailable for fif teen minutes in System II while Core Spray System I was out of service'for
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maintenance. Licensee A0 50-219/74-28 refers.
(Detail 4)
3.
In violation of Technical Specification Article 3.4.B.4, the Auto depressurization system initiation timers failed to complete their timing cycle in less than two minutes. Licensee A0 50-219/
74-33 refers.
(Detail 8)
Licensee Action on Previously Identified Enforcement Action Not inspected.
EthG Unusual Occurrences A.
Low Pressure MSIV Closure Switches The Low Pressure Main Steam Line MSIV closure pressure switches were found to trip at pressures less than the specified value. Licensee A0 50-219/74-35 refers.
(Details 3b and 9)
B.
Generator Load Anticipatory Scram Failure Pressure switch malfunction resulted in failure to trip on generator load rejection anticipstory scram. Licensee A0 50-219/74-30 refers.
(Detail 6)
C.
Relief Valve Out-of-Tolerance Settings Relief Valve pressure switches lA83B and 1A83D were found out of tolerance during routine surveillance. Licensee to RO A0 50-219/
74-29 refers.
(Detail 5)
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l-2-I Other Significant Findings
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.A.
Unresolved Items
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Shock Arrestors Two hydraulic shock and sway arrestors located on the Core Spray system were found inoperable. Licensee AO-50-219/74-31 refers.
(Detail 7)
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Current Findings
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The inspector reviewed the status of the licensee action as documented in the following Abnormal Occurrence reports.
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A0 50-219/74-24 (Detail 3a)
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A0 50-219/74-28 (Detail 4)
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3.- A0 50-219/74-29 (Detail 5)
4.
A0 50-219/74-30 (Detail 6)
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A0 50-219/74-31 (Detail-7)
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A0 50-219/74-33 (Detail 8)
7.
A0 50-219/74-35 (Detail 3b and 9)
Management Interview A management interview was held at the site on July 12, 1974 with the
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following attendees *
l Jersey Central Power & Light Company Mr.
D.'A. Ross, Manager, Nuclear Generating Stations Mr. D. L. Reeves, Chief Engineer Mr. E. Riggle, Maintenance Supervisor Mr. R. Stoudnour, Staff Engineer Mr. R. Swif t Maintenance Engineer The following summarizes items discussed, A.
Inspection Purpose The inspector stated.that the inspection was for a quarterly review of abnormal occurrences.
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B.
Abnormal Occurrences Discussed
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pyj The licensee's corrective action and his commitments related to-gjf the following abnormal occurrences were diocussed.
1.
A0 50-219/74-24 (Detail 3a)
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A0 50-219/74-28 (Detail 4)
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A0 50-219/74-29 (Detail 5)
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A0 50-219/74-30 (Detail 6)
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A0 50-219/74-31 (Detail 7)
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A0 50-219/74-33 (Detail 8)
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A0 50-219/74-35 (Details 3b and 9)
C.
Followup on Abnormal Occurrence Actions I
The inspector stated that the licensee's present method of controlling the completion of Abnormal Occurrence commitments appears ineffective.
zg g The licensee stated that, to ensure timely completion of corrective action, an administrative procedure would be developed and implemented to provide current status of corrective action on abnormal occurrences and action items assignments made upon review of abnormal occurrences by PORC.
D.
Snubber Replacement Status The inspector asked the licensee to address the present status of evaluation of mechanical snubbers.
The licensee stated that a continuing effort to replace the hydraulic snubbers with mechanical snubbers was in progress but had not yet been completed.
(Detail 7)
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DETAILS
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1.
Persons Contacted
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Mr. B. Cooper, Shift Foreman qad)
Mr. R. Dube, Q.A. Supervisor i v.
Mr. K. Fickeissen, Jr., Technical Engineer Mr. D. Ross, Manager Nucicar Generating Stations Mr. D. Reeves, Chief Engineer Mr. E. Riggle, Maintenance Supervisor Mr. R. Stoudnour, Staff Engineer Mr. R. Swift, Maintenance Engineer
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2.
General The inspector informed the licensee that a review of abnormal occurrences on a sampling basis will be made at approximatsly
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quarterly intervals.
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3.
Engineered Safety Feature Abnormal Occurrences a.
Stack Gas Particulate Filter Analysis The licensee's Abnormal Occurrence Report 50-219/74-24 was reported to RO:I as a violation of Technical Specification Article 4.6.B.l.g by licensee letter dated April 10, 1974, identifying the cause and details of the occurrence. PORC ggy minutes 29-74 documented review of the occurrence, which con-sisted of failure to analyze the stack gas particulate filter (for alpha, beta, and gamma activity) within one week of removal.
Limiting conditions for operation were not exceeded.
No increase in radioactivity release has been attributed to this occurrence. Counting of the filter 9 days af ter removal reportedly indicated comparibility to preceding and succeeding filter values.
7.ntended corrective action is to modify pro-cedural check off sheets to better control task accomplishment,
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with the PORC committed to revise the procedure on particulate counting to incorporate current memorandums and instructions.
This item is unresolved pending completion of corrective action.
b.
Main Steam Line Low Pressure Switches The licensee's Abnormal Occurrence Report 50-219/74-35 was reported to RO:I as a violation of Technical Specification Article 2.3.7 by licensee letter dated July 8, 1974. Three main steam line low pressure switches were found, during routine surveillance testing, to trip at values below the minimum trip
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-5-point of 860 psig. This occurrence represents an exceeding of a limiting safety setting which was detected and corrected by routine surveillance. The switches were reset and satisfactorily
,(T tested. Licensee generic treatment of switch drift problems is 1:4 discussed in Detail 9.
The inspector had no further questions on A0 50-219/74-3.
4.
ECCS Core Spray System The licensee's Core Spray system abnormal occurrence report A0 50-219/74-28 was reported to RO:I as a violation of Tech-nical Specification Article 3.4.A.1 by. licensee letter dated April 19, 1974. With core spray system I tagged out for main-tenance, the suction valve to the "B" core spray pump failed in the shut position during surveillance testing, causing a 15ss
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of core spray pump redundancy in System II.
Immediate corrective action consisted of manual realignment of the Core Spray system to re-establish redundancy. Further investigation revealed a
"B" spray pump suction valve bypass limit switch malfunction which was corrected by readjustment. Checks of similar valves showed no similar problem. Limiting conditions for operation were exceeded for 15 minutes as a result of this occurrence.
The inspector had no further questions on this item.
5.
Electromatic Relief Valve Pressure Switches M
Tripping of relief valves NR 108B and NR108D at 6 and 14 psig higher than the Technical Specification Article 2.3.4 limit of 1070 psig was reported to RO:I as a violation of a limit-ing safety system setting by licensee letter dated April 26, 1974 (abnormal occurrence report 50-219/74-29). PORC minutes 34-74 document licensee review of this item. Corrective action con-sisted of resetting and testing the switches. Licensee generic action on switch drifts is discussed in Detail 9.
The inspector had no further questions on A0 50-219/74-29.
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Generator Load Rejection Scram Generator Load Rejection Scram setpoint of 197 psig vs the 180 psig value prescribed by Technical Specification Table 3.1.1.A.12 was reported to R0:I as a violation of a limiting condition for oper-
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ation by licensee letter dated May 15, 1974 (abnormal occurrence report 50-219/74-29). PORC minutes 44-74 document licensee review of this item.
The switch was recalibrated and tested satisfacto-rily.
Licensee generic action on switch drifts is discussed in Detail 9.
The inspector had no further questions on A0 50-219/74-29.
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Shock and Sway Arrestors (Auxiliary System)
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The licensee's abnormal occurrence report A0 50-219/74-31 was 3 s forwarded to RO:I by licensee letter dated May 20, 1974. PORC thy minutes 46-74 document licensee review of this item. Two inoper-able units and five leaking units were found during licensee inspec-tion.
Corrective action consisted of replacement aith units having different (ethylene propylene) seals and tested to 4000 psig. The licensee has been evaluating replacing the installed hydraulic units with mechanical ones, but considers presently available mechan-ical units to have limited applicability in the reactor building.
This occurrence was reported as an item which, if uncorrected, threatened to cause the degradation of performance of an engineered safety feature in accordance with Technical Specification Article 1.15D.
The inspector had no further que.stions on A0 50-219/74-31.
8.
Automatic Depressurization System (Reactivity / Power Control)
Failure of the automatic depressurization system Initiation Timers to complete this cycle within 2 minutes was reported to RO:I by licensee letter dated May 22, 1974 (A0 50-219/74-33) as a violation of a limiting condition for operation established by Technical Spec-ification Article 3.4.B.4 PORC minutes 46-74 document licensee review of this item.
Corrective action consisted of resetting and testing the timers to complete their cycle in less than 105 seconds. The inspector questioned the surveillance procedure absence of instructions IME to the operator to set the timers and the licensee stated that the procedure would be revised.
Pending completion of that revision, this item is unresolved. The inspector had no other questions on A0 50-219/74-33.
9.
Switch Drift Abnormalities The licensee reviewed with the inspector the progress of his contin-
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uing corrective actions to resol e the high percentage of total
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reported abnormal occurrences in the area of switch drifts and/or repeatability of settings.
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This problem has occurred in the licensee surveillance program that monitors the settings of the Main Steam Line Low Pressure Switches.
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Seven of the licensee's reported abnormal occurrences reported to the AEC in 1974 involve these switches.
a.
NSSS Supplier Action The inspector reviewed licensee's correspondence and NSSS supplier replies to questions concerning the basis for the steam line low pressure setting of 850 psig. The licensee has requested the NSSS
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to pursue the development of a Technical Specification change to lower the set point. The NSSS supplier correspondence
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reviewed by the inspector showed no substantive progress on the j(J problem.
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b.
Licensee Testing The inspector discussed with the licensee his program of testing of two additional switches. The data reviewed did not eliminate the zero tolerance presently necessary on the range of switch l
settings. Additional test results'from the NSSS supplier did-not provide any new ideas to resolve the problem. The switches tested would still be subject to a 1% tolerance on repeatability.
The inspector viewed the licensee's testing area, and the piping configuration and readout lamps on the test rig. ConEinuing data
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l accummulation in this area appears to confirm the licensee state-ment that the switch tolerance problem should be vigorously pur-l sued in order to decrease the number of switch drift abnormalities.
The areas discussed will be reviewed for continuing progress at a subsequent inspection. This item is unresolved.
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