IR 05000219/1974007
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U. S. ATOMIC ENERGY C0:011SSION
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DIRECTORATE OF REGULATORY OPERATIONS
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REGION I
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... a 50-219
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RO Inspection Report No.:
50-219/74-07 Docket No.:
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DPR-16 Licensce:
Jersey Central Power and Light Company g
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Madison Avenue at fonch Bowl Road
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Morristown, New Jersey 07960 C
Category:
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,0yster Creek, Fork,ed River, New Jersey
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' Type of Licensee:
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Routine, Unannounced
' Type of Inspection:
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Dates of Inspection:
Dates of Previous Inspection:
. Pril 22-26, 1974
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Reporting Insp6ctor:
0 0. k N. )* *,. b
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f[gy/7y D. F. Johnson, Reactor Inspector DATE
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Nucidar Support Section
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DATE
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Accompanying Inspectors:
8 G AM, h, A g/g/7y
E. C. McCabe Senior Re'act6r Inspector DATE Reactor Operations Branch
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DATE
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None Other Accompanying Personnel:
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Reviewed By:
[ 6d N, h c.,
gf[y/7
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E. C. McCabe, Senior Reactor Inspector DATE Reactor Operations Branch
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9604250131 960213
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SUMMARY OF FINDINGS _
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Enforcement Action
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None
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Lfe,ensee Action on Previously Identified Enforcement Actions i
Not Inspected Unusual occurrences
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None Identified
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- Other Significant Findings A.
Current Findings
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80% of procedures previously identified as lacking in scope of
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coverage with respect to Regulatory Guide 1.33 remain to be
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completed.
(Detail 2)
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Station organization was examined f or compliance with Minimum 84k'
Shif t Nbnning Requirements for Nuclear Power Plants.
(Detail
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RO:I reviewed selected Facility Procedures and provided comments 3.
to the licensee.
(Detail 4)
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4.
The licensee's corrective actions on the following Abnormal
Occurrences were examined.
a.
A0 50-2).a-74/17 (Detail 5)-
b.
A0 50-21,. 74/18 (Detail 6)
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c.
A0 50-219: 74/19 (Detail 7)
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A0 50-219: 74/20 (Detail 8)
A0 50-219:' 74/21- (Detail 9)
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A0 50-219: 74/23.(Detail 10)
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-A0 50-219: 74/27 (Detail 6)
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Statua of Previously Reported Unresolved Items
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50% of corrective actions resulting from. abnormal occurrences remain to be completed during this refueling outage.
(Details 5-11)
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Current Unresolved Items 4li~'f
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Shift Manning Requirements (Detail 3)
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Facility Procedures (Detail 2, 3)
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Corrective Actions - Abnormal Occurrences (Detail 5-10)
Management Interview Personnel Attending i
Mr. J. T. Carroll, Jr., Station Superintendent
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Mr. D. L., Reeves, Chief Engineer
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NW. E. Crowney, Technical Engineer
Mr. J. Sullivan, Jr., Operations Engineer Mr. R. Swift, Maintenance Engineer Mr. K. Fickeissen, Technical Supervisor Mr. E. Riggle, Maintenance Supervisor The following summarizes items discussed:
A.
Status of Facility Procedures Program.
(Detail 2)
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Shift Manning Requirements.
(Detail 3)
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RO:I Review of Facility Proceduros.
(Detail 4)
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Status of Previously Identified Unresolved Items.
(Details 5-11)
E.
QA Program for Operations.
(Detail 11)
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Training and Retraining Program.
(Detail 12)
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DETAILS
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Persons Contacted Mt. J. T. Carrol, Jr., Station Superintendent Mr. D. L. Reeves Chief Engineer Mr. J. Sullivan, Jr., Operations Engineer Nr. R. Swif t, Maintenance Engineer Nb. R. Dube, QA Supervisor Mr. K. Fickeissen, Technical Supervisor Mr. J. P. Maloney, Operations Supervisor
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2.
Status of Facility Procedures Program Procedural coverage lacking as identified in R0 Report 50-219/
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73-22.
(1)
Authorities and responsibilities of the plant staff for safe operation of the facility.
The licensee stated Administrative Procedure 103.2 "Organi-zation and Responsibilities" contains partial responsi-bilities and that the inspector's comments pursuant to ANSI N18.7 - 1972 Section 5.1.1 would be incorporated
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duf into Administrative Procedure 103.2.
(2)
Shif t and Relief Turnover.
The licensee stated Section 103.12 of Administrative Pro-cedure 103 " Organization and Responsibility" has been added and contains instructions for relief and shift turnover.
The inspector reviewed Administrative Procedure 103 and stated he had no further questions in this area.
(3)
Record Retention and Retrievability.
The licensee stated a procedure has been written and is in draft form.
(4) Procedure Adherence.
The licensee stated a procedure has been written and is in final draft form.
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e (5)- Surveillance Test and Calibration Schedules.
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reviewed'and is in draft form.
i (6) Bypassing of-Safety Functions and Jumper Control.
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The licensee stated Administrative Procedure.103 has been revised and includes procedures for bypassing safety
functions and jumper control.
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The inspector reviewed this procedure and had no further questions.in this area.
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(7) Implementing the Corrective and Preventive Maintenance
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Program.
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The licensee stated administrative controls for the implementation of the Corrective and Preventive Program
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have been written and are in final draf t.
(8) Procedure Preparation.
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The licensee stated an administrative procedure for isya procedure control is in final draft, contains.instruc-
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tions on procedure preparation pursuant to ANSI'N18.7 and i..
R0 Guide 1.33, and describes the review and approval process.
(9)
Communication System.
The licensee stated that administrative procedures will
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be written for the facilities communication systems.
i Items (1), (3), (4), (5), (7), (8), (9) preceeding remain
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unresolved.
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I The licensee stated all Facility Procedures would be reviewed and revised accordingly pursuant to ANSI N18.7.
The licensee
further stated a purchase order has been written to obtain an outside consulting firm for the review and updating of Facility
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Procedures.
4-This item remains unresolved.
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Shif t Manning Requirements
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The inspector discussed, with the licensee, current licensing guid-4 w.
(Q ance on shif t manning requirements for nuclear power plants.
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licensee's current shif t manning appears to be in conformance with these considerations with the following exceptions, Regulatory guidance states in.part: "The management of each
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station having one or more units containing fuel should either-(1) qualify and designate at least one nenber of each shift operating crew to implement radiation protection procedures, including routine or special radiation surveys using portable radiation detectors, uses of protective barriers or signs, use of protective clothing and breathing apparatus, perfofmance of L contamination surveys, checks on radiation monitors, and limits of exposure rates and accumulated dose, or (2) assign a
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health physics technician to each shift".
I The licensee does not currently have radiation-protection personnel assigned to the back shif ts.
Health physics cover-age is provided on the day shift only, b.
Control Room Surveillance during Scheduled Non-Steady Opera-tion.
W Regulatory guidance states:
"Two licensed operators should be in the control room of a unit during (a) startup from cold shutdown, (b) scheduled shutdowns, and (c) recoveries from trips or unscheduled or unexplained power reductions.
At least one of these operators should possess a Senior License for condition (c)".
The licensee presently does not require that a Senior Licensed Operator be present in the control room during a recovery' from a reactor trip or an unscheduled or unexplained power reduction.
Refueling and Irradiated Fuel Handling Operations.
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Regulatory guidance states:
"A Senior Licensed Operator with no concurrent operational duties should directly supervise irradi-ated fuel handling and transfer activities and fuel assembly transfers into or out of a reactor vessel".
The licensee currently assigns the responsibilities and auth--
ority for the handling of fuel in or out of the reactor vessel to licensed operators without requiring the presence of a senior licensed operator to direct the tuel handling activities, e
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The inspector stated that the above exceptions to Regulatory guidance on shif t manning requirements are not in violation of yTJ any current AEC rule, regulation or condition of the present
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facility license or Technical Specifications. However, these
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items remain unresolved pending further evaluation.
4.
Facility Procedure Review Comments resulting from RO:I review of " Integrated Primary a.
Containment Leak Rate Test" procedure are as follows:
(1) The prerequisites are lacking the following specifics:
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(a) Identification or status of test device c1'eanliness with respect to possible contamination.
Test devices used on contaminated or possibly con-taminated systems and components should be clearly identified, stored and utilized separately from uncontaminated test devices.
(b) Test devices used on contaminated or possibly con-taminated systems and components should have isola-tion and disconnect capabilities to prevent contam-
>@4 ination from components being tested and test sources.
These precautions should be stated in prerequisites.
(c) Absoluta filters should be installed on test device vent lines when testing possibly contaminated com. -
ponents.
(2) Precautions are lacking in specific detail relative to radiological controls and equipment necessary for the
performance of the test.
(3) A valve lineup checksheet and signoff should be provided for the installation and removal of test devices.
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(4) Step by step instructions are not indicated for each penetration.
i (5) Spaces are not provided for signoffs of prerequisites.
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Data sheets are not attached to procedures to verify data to be recorded and data taken.
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Restoration is not specific - valve operation and final position should be specified, methods forLbleedoff, ca'p-
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included in restoration procedures.
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The licensee concurred with the above comments and agreed to revise the procedure for inclusion of the inspector's comments.
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This item is resolved.
5.
SB Startup Transformer Failure of Breaker Operation - A0 50-219:
74/17 Corrective Action
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All 4160 volt safeguard and 460 volt safeguard switchgear will be
checked to see that closing springs have been properly changed.
In addition, the feasibility of installing a closing circuit monitoring.
system will be explored with the Generation Engineering Department.
Licensee's Actions The licensee replaced the faulty coil and cam switch and checked all safeguard breakers for proper charging action and found them satisfactory. The Generation Engineering Department is currently
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evaluating the possibility of installing a closed circuit breaker monitoring system, no conclusions or actions have been completed on this matter.
This item remains unresolved pending the results and actions by the
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' Generation Engineering Department.
Hydraulic Shock and Sway Arrestor Failures - A0 50-219:74/18, 74/27 6.
Corrective Action
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Pressure tests will be run on the defective units in an attempt to
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determine the cause of their inoperability and then each of the units will be dismantled to visually determine seal status.
In addition, during the present refueling outage, the licensee plans
.to replace these units and others in the primary containment which still contain molded polyurethane seal material with units rebuilt
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exclusively with ethylene propylene material.
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Licensee's Actions All snubber units have been inspected and pressure tested.
Visual examination identified deterioration of.the molded polyurethane
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seal resulting in loss of hydraulic fluid. All snubbers in the drywell have been installed and seals replaced with ethylene pro-
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pylene material.
This item is resolved.
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Violation of Containment Integrity - A0 50-219:74/19 Corrective Action The operator retraining program will emphasize that all available
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indications are to be used when critical parameters such as reactor wata. temperature are being monitored.
In addition, the operators
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The shutdown log will be reviewed and modified to require the re-cording of additional system temperatures related to the reactor coolant temperature.
Licensee's Actions The licensee has incorporated into the operator's retraining program the subject of recorder traces and confirming indications ifrom some 184%
other source. Operators have been instructed regarding straight
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recorder traces and utilizing other indications for conformation of critical parameters.
In addition, the shutdown log has been modi-
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fled to include additional monitoring from the multi temperature recorder to confirm reactor water temperature.
This item is resolved.
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Main Steam Isolation Valve Leakage - A0 50-219:74/20 Corrective Action Main steam isolation valve NSO4A will receive complete preventive maintenance and NSO4B will be inspected and completely repacked.
Licensee's Actions
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Main steam isolation valve NSO4A is completely disassembled under-going inspection preventive maintenance.
Valve NSO4B will be repacked.
This item is unresolved pending completion of preventive maintenance and reassembly of NSO4A and repacking of NSO4B.
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Main Steam Line High Flow Sensor Inoperable Due to Improper Valve Lineup - A0 50-219:74/21 1.9 ',
'/J Corrective Action Instrument Technicians will be advised via a memorandum of the details of this event, the critical importance of valve lineup checks on systems associated with reactor protection.'and the importance of immediately reporting instances in which valves are found to be incorrectly positioned.
Licensee's Actions
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Instrument technicians have been instructed in the importance of
valve checkoff lists and their relationship to plant safety. The retraining program will cover this area for all operating personnel prior to startup.
This item is unresolved pending knplementation of the above subj ect matter into the retraining program.
10.
Isolation Condenser High Flow Sensor - High D/P Actuation -
A0 50-219:74/23 344 Corrective Action
- Af ter evaluation it has been concluded that changing the trip set point of the isolation condenser condensate high flow line break sensors from 27 inches of water to 24 inches of water and the trip set point of isolation condenser steam high flow line break sensors from 20 PSIG to 15 PSIG will not adversely affect the isolation function of these sensors under transient conditions.
The appro-priate procedures are now being revised in preparation for implemen-
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ting these set point changes.
Licensee's Actions The licensee has revised the appropriate procedures and changed the set points of the high flow steam break sensor from 20 to 15 PSIG and the high flow line break sensor from 27 inches to 24 inches of water.
This item is unresolved pending an operability check.
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-10-11. QA Program for Operations
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Of9 Most of the implementing procedures are in final draft and the
program would be submitted to the AEC within a week.
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Training and Retraining Programs The inspector informed the licensee that RO:I would be conducting a review of the training and retraining programs for-implementation.
The review would cover both licensed and non licensed training pur-suant to ANSI N18.1, ANSI N45.2.6, 1973 as modified for Regulatory Guide 1.58,10 CFR Part 19,10 CFR Part 50, Appendix B, Criterion
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