IR 05000269/1974005
| ML19317E487 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 08/09/1974 |
| From: | Epps T, Long F NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19317E472 | List: |
| References | |
| 50-269-74-05, 50-269-74-5, NUDOCS 7912180729 | |
| Download: ML19317E487 (18) | |
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AUG M 1974 RO Inspection Report No. 50-269/74-5 Licensee:
Duke Power Conpany Power Building 422 South Church Street Charlotte, North Carolina 28201 Facility Nane: Oconee Unit 1 Docket No.:
50-269
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License No.:
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Category :
C Location:
Seneca, South Carolina Type of License:
, Type of Inspection:
Routine, Unannounced Dates of Inspection:
July 10-12, 16-18 and 24-26, 1974 Dates of Previous Inspection: April 18-19 and"23-26, 1974
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Principal Inspector:
T. N. Epps, Reactor Inspector (July 16-18 & 24-26, 1974)
Facilities Operations Branch Acc6npanying Inspector:
G. R. Jenkins, Radiation (July 10-12, 1974)
Specialist, Radiological and Environnental Protection Branch Principal Inspector:
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V 9 2. M T. N. Epps, Readtdr Inspector
Da't e
Facilities Operations Branch Reviewed By N
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F. J. Long, Chief Y
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Facilities Operations Branch
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79121807M
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RO Rpt. No. 50-269/74-5-2-
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sum!ARY OF FINDINGS The purpose' of this inspection was to follow up on unresolved items, abnormal occurrences, previous violations and to conduct a gent. 1 operations inspection of Unit-1.
I.
Enforcement Action A.
Violations The following violations are considered to be category II, severity.
1.
Condensate Test Tank Not Sacpled Before Release Oconee Technical Specification 3.9.8. requires liquid radioactive waste sampling and activity analysis of the condensate test tank contents prior to release.
Contrary to the above on April 24, 1974, a release was made from the B condensate test tank without prior sampling.
Corrective actions described in DPC1s abnormal occur-rence report dated Iby 6, 1974, were reviewed and the inspector had no further questions.
(Details I, paragraph 8)
2.
Reactor Coolant System Pressure Transmitters Oconee Technical Specification 2.3 requires that the high.
reactor coolant system pressure setpoint be no greater than 2355 psig.
Contrary to the above surveillance tests conducted during thy, 1974, showed pressure setpoints to be above 2355 psig.
Corrective actions described in DPC's abnormal occurrence report dated >by 17, 1974, were reviewed and the inspector had no further questions.
(Details I, paragraph 10)
3.
Main Steam Stop Valve Closing Time Oconee Technical Specification 4.8.1. requires a closing
. time of 15 seconds or less for channel B when testing main steam stop valves.
Contrary to the above on May 10, 1974, a periodic test yielded closing times of 15.0, 23.0 and 22.5-seconds for three Unit 1 main steam stop valves.
Corrective actions
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described in DPC's unusual event report dated June 7, 1974, were-reviewed and the inspector had no further questions.
(Details I, paragraph 11)
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R0 Ept. No. 50-269/74-5-3-
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B.
Safety Items None II.
Licensee Action on Previously Identified Enforcement Matters A.
Violations 1.
High Radiation Areas (R0 Inspection Report Nos. 50-269/74-3 and 50-270/74-2, Item I.A.l.a.)
Duke Pcwer Company's response, dated May 24, 1974, stated in part, that plans were being made to install doors capable of being locked in other rooms in the Auxiliary Building which could be high radiation areas, and that this would allow control to be established if control of these areas were required by 10 CFR 20.203.
Contrary to this statement, and to 10 CFR 20.203, two rooms in the Auxiliary Building, which were posted as high radiation areas, had no doors nor other access control mechanism installed.
Duke Power Company's response also stated, in part, that the General Office health physics staff would give increased direction and technical support to the activities of the Station health physics section, including direct participation in design improvements and station modifications.
A Statido Modification Report was submitted by the Station health physics section on April 11, 1974, to fabricate and install metal doors to control high radiatien accas as they occur, yet no tangible action had resulted three months later.
(Details II, paragraph 2)
2.
Evaluating, Correcting and Reporting Radiological Problems (R0 Inspection Eeport Nos. 50-269/74-3 and 50-270/74-2, Item I.A.l.b.)
Duke Pcwer Company's respense, dated May 24, 1974, was verified by the inspector.
There are no further questions on this item.
(Details II, paragraph 3)
3.
Personnel Survey Instruments (R0 Inspection Report Nos. 50-269/74-3 and 50-270/74-2, Item I.A.l.c.)
Duke Power Company's response, dated >by 24, 1974, was verified by the inspector.
There are no further questions on this item.
(Details II, paragraph 4)
4.
Health Physics Procedures (R0 Inspection Report Nos. 50-269/74-3 and 50-270/74-2, Item I.A.l.d.)
Duke Power Company's response, dated >Sy 24, 1974, was reviewed with licensee representatives.
Review and revision of health
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physics procedures is in progress; a new completion date of Septemb2r 1, 1974, was provided.
(Details II, paragraph 5)
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R0 Rpt. No. 50-269/74-5-4-
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Unit Vent Particulate Air Monitoring (R0 Inspection Report Nos.
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50-269/74-3 and 50-270/74-2, Item I.A.l.e.)
24, 1974, uas revicued and additional Duke's reply dated May information requested regarding actions taken to date or planned to correct these problems.
(Detai30 II, paragraph 6)
6.
Process Radiation Monitor Setpe4r. s (R0 Inspection Report Nos.
5-269/74-3 and 50-273/74-2, Item I.A.l.f.)
Duke's reply dated May 24, 1974, was reviewed and additional infor-mation requested to include identification of specific setpoints for this equipment.
7.
Radioactive Gas Releases (R0 Inspection Report Nos. 50-269/74-3
.and 50-270/74-2, Item I.A.1.g.)
Duke Power Company's response, dated May 24, 1974, was verified There are no further questions on this item.
by the inspector.
(Details II, paragraph 7)
Nuclear Safety Review Committee (R0 Inspection Report Nos.
8.
50-269/74-3 and 50-270/74-2, Item 1 A.2.a.)
Duke Power Company's response, dated May 24, 1974, was reviewed There are no further comments on this item.
by the inspector.
(Details II, paragraph 8)
9.
Poeting Notice of Violations (R0 Inspection Report Nos. 50-269/74-3 and 50-270/74-2, Item I.A.2.b.)
Duke Power Company's respor.se, dated Iby 24, 1974, was verified There are no further questions on this itec.
by the inspector.
(Details II, paragraph 9)
10.
Violations previously identified in reports 50-269/74-1 and
50-269/74-2 are considered to be closed.
B.
Safety Items l
None III.
New Unresolved Items
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74-5/1 The licensee's program for power escalation testing has not been completed for Unit 1.
(Details I, paragraph 14)
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RO Rpt. No. 50-269/74-5-5-
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IV.
Status of-Previously Reported Unresolved Items 71-7/1 Valve Wall Verification Program
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This item is closed.
(Details I, paragraph 2)
73-12/1 Calibration of Effluent Monitors
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No change 73-13/1 Wastewater Collection Basin Modification i
No change
73-13/2 control Rod Failures i
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No change i
74-2/1 Control of Materials, Parts and Components It was verified that an approved procedure is in effect.
This
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i item is closed (Details I, paragraph 3)
74-2/2 EP/0/A/1800/16 " Loss of Power"
This procedure now covers degraded power sources.
This item is closed.
(Details I, paragraph 5)
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74-2/3 High Activity in The RCS
.This procedure has been written and approved.
This item is
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closed.
(Details I, paragraph 6)
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i 74-2/4 Loss of Component Cooling Water System This procedure has been apprcved.
Ulis iten is closed.
(Details I, paragraph 4)
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74-3/1 Measuring and Reporting of Effluents i
The licensee's program for measuring and reporting of effluents
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i has been altered in the areas.previously noted.
This item is-closed.
(Detai.ls II, paragraph 10)
74-3/2 ' solid Waste Shipping Containers
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The licensee has : implemented an inspection program for shipping containers.
This item is closed.
(Detcils II, paragraph 11)
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74-3/3 -Training of Unlicensed Utility operators
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V.
Unusual Occurrences A.
A.O.-269/74-2 Isolation of Keewee Under2round Feeder No further questions.
(Details I, paragraph 7)
B.
A.O.-269/74-7 Condensate Test Tank Not Sampled Before Release No further questions.
(Details I, paragraph 8) (Summary I. A.l.a.)
C.
UE-269/74-1 Keowee Unit-2 Emergency __' tart Test No further questions.
(Details I, paragraph 9)
D.
A.O.-269/74-8 Reactor Coolant System Pressure Transmitters No further questions.
(Details I, paragraph 10) (Summary I. A. l.b. )
E.
U.E.-269/74-2 Main Steam Stop Valve Closing Time No further questions.
(Details I, paragraph 11) (Summary I. A.i.c.)
F.
A.O.-269/74-10 Gasecus Release During LDST Sampling Corrective action described in DPC's report, dated July 1,19 74, were discussed with licensee representatives.
This item remains open.
(Details II, paragraph 12)
VI.
Other Significant Findings
- ersonnel and Organizational Changes Mr. J. N. Pope is new the Assistant Operating Engineer on Unit 1, replacing Mr. I. L. McConnell, who transfered to another DPC facility.
VII. Management Interview interview was held on July 12, 1974, with G. R. Jenkins' management the folicwing DPC management representatives present with other DPC representati-es :
J. E. Srith - Plant Superintendent J. W. Hampten - Assistant Plant Superintendent R. M. Koehler - Staff Engineer 0. S. Bradham - Technical Support Engineer C. L. Thates - Health Physics Supervisor
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R0 Rpt. No. 50-269/74-5-7-
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Items discussed included items II. A.1. and II. A.4 The mana3ement interview for the portions of the inspection conducted by T. N. Epps was held in two parts on July 18, 1974 and July 26, 1974.
The following DPC personnel were present each time:
J. E. Smith - Plant Superintendent J. W. I!ampton - Assistant Plant Superintendent R. M. Koehler - Staff Engineer L. E. Schmid - Operating Engineer O. S. Bradham - Technical Support Engineer Among items discussed were the three violations in Section I of this su= mary and the new unresolved iten in Section III.
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RO Rpt. No. 50-269/74-5-I-1 DETAILS l'
Prepared By:
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M I 7 74-T. N. Epps, ReicL6r Inspector
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Facilities Operations Branch Dates of Inspection:
July 10-12, 16-18, 24-26, 1974
?!7V Reviewed By
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F. J. Lodg, Chief Date
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Facilities Operations Branch
1.
Individuals Contacted
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Duke Pcwer Company '(DPC)
J. E. Smith - Plant Superintendent
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R. M. Koehler - Statf Engineer
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L. E. Schmid - Operating Engineer C. L. Thames - Health Physics Supervisor
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J. N. Pope - Assistant Operating Engineer J. T. Campbell - Shift Supervisor
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J. Cox - Station Senior Quality Assurance Engineer 2.
Thin Walled Valves Revision 4 to the Duke Power Company, Oconee Valve Wall Thickness Verification Program has been reviewed by Region II Construction Branch personnel and there are no further com=ents at this time regarding Unit 1.
3.
Control of Material, Parts and Components The inspector verified that an approved procedure exists to control cocponents to stock for reuse after repairs.
The station senior quality assurance engineer indicated that this-pro'cedure covers control of CRD stators, RC pump seals, and reactor building spray pump parts.
4.
Emergency Procedure for " Loss of Component Cooling Water,"'
This emergency procedure was approved on June 27, 1974, by the Plant: Superintendent.
The inspector reviewed this procedure and had no further questions.
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R0 Rpt. No. 50-269/74-5 I-2
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Emergency Procedure for " Loss of Power" The inspector reviewed this procedure and verified that it was revised to include degraded power sources.
The procedure was approved by the Plant Superintendent on April 26, 1974.
6.
Emergency Procedure for "High Actlyity in the RCS" This procedure was approved on June 20, 1974.
A licensee representa-tive indicated that the intent of this procedure is to have reactor operations personnel notify site management if repetitive alar =s are annunciated due to high activity in the reactor coolant system.
It was also stated that the intent is to shut the reactor down
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before the technical specification limit on reactor coolant activity is exceeded.
7.
Isolation of Keowee Undereround Feeder (A0 50-269/74-2)
This item involved a lockout of the Keowee Unit 2 generator due to electrical grounding.
This incident was r,eported by the licensee on February 22, 1974, in Abnormal Occurrence report No. 50-2'9/74-2.
The licensee's corrective action was to review the grounding.
system to identify potential problems and to check the control room
"Keowee Unit 2 Emergency Lockout" annunciator for operability.
, This problem has not recurred to date.
8.
Condensate Test Tank Not Sannled Before Release Oconee Technical Specification 3.9.8 requires liquid radioactive waste sampling and activity analysis of the condensate test tank contents prior to release.
Contrary to the above on April 24, 1974, a release was made frca the 3 condensate test tank without prior sampling.
This incident was reported by the licensee on May 6, 1974, in Abnormal Occurrence report No. 50-269/74-7.
The cause of this incident was operator error.
Corrective action was to clearly identify the condensate test tank isolation valves and to modify the procedure for releasing liquid. waste to require verification by the operator that all steps have been conpleted prior to release.
The inspector verified this corrective action.
There are no further questiens at this time.
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R0 Rpt. No. 50-269/74-5 I-3 9.
1:eowee Unit 2 Ecercency Start Test on April 23, 1974, during a Keowee Hydro Emergency Start Test, Keowee Unit 2 started as required but tripped after 15 seconds.
This incident was reported by the licensee on May 6, 1974, in Unusual Event report No. 50-269/74-1.
It was determined that a te=porar. low oil level indication dt e to the rapid start was the cause of
~ trip.
The licensee's corrective action was to install a 40 seconc ice delay on the low oil lesel relay to avoid erroneous low oil level indications after rapid starts.
The inspector had no further questions on this item.
10.
Reactor Coolant Systen Pressure Transmitters Oconee Technical Specification 2.3 requires that the high reactor coolant system pressure trip setpoint be 2355 psig maxi =um.
Contrary to the above, on May 7, 1974, pressure transmitters RC3A-PT1, RC3A-PT2, RC33-PT1 and RC3B-PT2 were found to be out of calibra-tion during surveillance testing.
These transmitters provide inputs to the reactor protection system.
This incident was reported by the licensee on May 17, 1974, in Abnormal occurrence report No. 50-269/74-S.
The licensee's corrective action was to recalibrate the transmitters and to increase frequency of calibration to be performed on a quarterly basis until reliability is verified.
A licensee representative stated that the reactor coolant system pressure transmitters had been checked on Oconee Unit 2 and were within calibration limits.
There are no further questions at this time.
11.
Main Steam Stop Valve Closing Time Oconee Technical Specification 4.8.1 requires a closing time of 15 seconds or less for channel 3 when testing main steam stop valves.
Contrary to the above on May 10, 1974, a periodic test yielded closing tines of 18.0. 23.0, and 22.5 seconds for three Unit 1 main secam stop valves.
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This was reported by the licensee on June 7, 1974, in Unusual Event report No. 50-269/74-2.
The licensee's corrective action was to remove orifices from the valve actuato-drain ports to allow faster closing times.
The valves were rs tested yielding acceptable closing times.
12.
Control Room Records The inspector reviewed samples of the control room log sheets and log book and the shift supervisor's log book for the two week period ending July 24, 1974.
The jumper log was also reviewed for the months of June and July 1974.
The inspector had no significant comments on this review.
13.
Plant Tour The inspector toured the facility including observations in the control room, portions of the auxiliary building, and portione of
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the turbine building including the high energy line insr:11ed during the last shutdown.
Housekeeping in' a portion of the turbine building appeared to be lacking and a high radiation area sign was observed in the turbine building where no high radiation area existed.
These comments were given to site management.
The high radiation area sign was removed before the inspector left the site and the licensee stated that work was planned to cleanup the portions of the turbine building in question.
14.
Power Escalation Testing Four power escalation tests have not been run on Unit 1.
These are:
TP/1/B/800/8
- ICS Tuning at Power
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TP/1/B/800/13 - Unit Loss of Electrical Lead TP/1/A/800/14 - Turbine Reactor Trip Test TP/1/A/800/29 - Unit Load Transient Test in addition to the above, TP/1/C/700/7, " Core Pressure '> rop Test,"
has not been completed and finally approved and TP/1/A,800/27,
"incore instrument Calibra tion" test results have not received final approval.
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Licensee management agreed to establish a target date for completing the above tests by the end of August 1974 This will be carried as an unresolved item.
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i R0 Rpt. No. 50-269/74-5 II-l r
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- DETAILS II Prepared by:,
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G. R.' JecKins, Radiation Specialis t Date Radiolohical and Environmental
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Protection Branch Dates of Inspection: July 10-12, 1974
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Reviewed by:
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){ T. Su:'herlarid, Chief Date
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Radiological and Environ = ental Protection Branch t
1.
Individuals Contacted J. E. Smith - Plant Superintendent J. W. Hampton - Assistant Plant Superintendent L. E. Schmid - Operating Engineer R. M. Koehler - Staff Engineer C. L. Thames - Health Physics Supervisor
C. T. Yongue - Assistant !;ealth Physics Supervisor M. C. Williacs - Assistant Health Physics Supervisor
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M. G. Kriss - Assistant Health Physics Sup'ervisor K. Reed - Assistant Shift Supervisor
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2.
The licensee response to this violation was reviewed.
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An inspector toured the second floor level of the Auxiliary Building to determine if Rcom 104 and other high radiation areas were properly posted and cen*. rolled.
Room 104 was posted as a radiation area (caximum dosc. rate of 50 =illirem/ hour at contact with the Bleed Holdup Tank), and the inspector v -ified that a retal door with locking device had been installed.
However, two roons (Roon 208 " Pipe Chase" and Room 214 "Deminerali::er Hatch Area") which were posted i
as high radiation areas (tmicus dose rates of 280 millirem / hour and 300 millirem / hour, respectively) had no positive personnel access control
as required by 10CFR 20.203(c)(2),
The Health Physics Supervisor i
stated that a Station Modification Report had been submitted to l
l Charlotte on April 11, 1974 to fabricate and install cetal doors to i
control high radiation areas as they occur.
He further stated that a call to Charlotte during the inspectien revealed that the
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l codification was delcyed in the General Office (Charlotte) administrative
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approval circuit.
The Health Physics Supervisor initiated an on-site-
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work requast on July 12, 1974, to fabricate and install barricades at
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the high radiation area entrances.
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RO Rpt. No. 50-269/74-5 II-2
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3.
Evaluating, Correcting and Reporting Radiological Preblers The licensee response to this violation was reviewed.
An inspector verified that the licensee has initiated a program for evaluating, correcting and reporting radiological proble=s.
Four Health Physics Preblem Reports have been initiated since the inception of this program; these were reviewed by the inspector.
The inspector had further questions concerning this ite=.
no 4.
Personnel Survey Instruments The licensee response to this violatien was reviewed.
Records of the daily response check of personnel survey instruments (RM-14)
were reviewed, and.a spot check of operability of the instruments was made. The inspector had no further questions en this item.
5.
Health Physics Procedures The licensee response to this violation was reviewed.
An inspector
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reviewed Administrative Procedure No.17 for control of health physics precedures. The current status of the review and revision of health physics procedures was discussed.
A licensee representative esti=ated that about 667. of the procedures have been revised and are in the approval process.
The Health Physics Supervisor stated that all revised health physics procedures will be issued by September 1, 1974.
6. ' Unit Vent Particulate Air Monitoring The licensee response to this violatica was reviewed.
An inspectcr reviewed records of the analyses of daily air samples from the Unit 1 and Unit 2 vents. A supplemental respense to this ite: has been requested, to include an esti=ated date when the prcblems with the unit vent particulate =cnitors will be resolved.
7.
Radioactive Gas Releases l
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The licensee response to this violation was reviewed.
An inspecter discussed waste gas releases with an assistant shif t supervisor, who was knowledgeable of the requirement to coordinate releases with f avorable =cteorological conditions.
The inspector observed the tenperature recorder chart for the period of the two most recent waste gas releases; neither were =ade during an atraspheric inversion.
A licensee representative stated that gaseous waste releases gre now coordinated with faverable retecrological conditions. The inspector had no further questions en this ite=,
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R0 Rpt. No. 50-269/74-5 II-3 8.
Nuclear Safety Review Ccemittee
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The licensee respense to this violation was reviewed.
An inspector reviewed the minutes of the NSRC meeting of June 4-5, 1974. Although the radioactive gas release incident of February 8,1974 was not discussed, the minutes were generally core descriptive than those previously review ;4 The inspector had no further connent on this item.
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9.
Posting Notice o._ Violations The licensee response to this violation was reviewed.
An inspector verified that the licensee has established a techanism for posting notices required by 10 CFR 19, and observed that a notice of violations was posted.
The inspector had no further questions on this item.
10. Measuring and Reporting of Effluents (74-3/1)
A prist inspection had revealed that so=e aspects of the licensee's pregram for ceasuring and reporting of effluents were not in accordance with guidance provided by AEC Regulatory Guide 1.21.
An insp.ctor reviewed these ite=s with a licensee representative, and was informed that:
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The release rate of tritium from the plant vents is now deternined a.
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by qnarterly sampling; b.
The tinimum detectabic activity (MDA) for gacra analysis of each isotope in liquid radwaste is new 5x10-7 microcuries per tilliliter; Results of particulate activity released during the period c.
July - Dece=ber 1973 have been corrected and sent to Charlotte for review. The corrected released activity will be reported in the semi-annual report for January - June 1974 ;
d.
The licensee has evaluated the catheds used for accounting for gaseous activity released.
In order to insure that any uncertainty is on the conservative side, the existing rethod will be continued until a planned i= prove =ent in data input to the co=putar is implemented.
The inspecter had no further questions en this item.
11. Solid Naste Shipping Containers (74-3/2)
A pricr inspection had noted that the licensee had no program for inspecting easte drums to assure compliance with applicable DOT s,
regulations. A licensee representative stated that a drum inspection
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program has been imple ented, and that a procedure will be written covering the inspection program.
The inspector had no further questions on this item.
12.
Gaseous Release During LDST Sanpling (AO-269/74-10)
An inspector discussed the licensee's report of this release with licensee representatives.
A similar incident had occurred during the previous sampling of the letdcwn storage tar.x, as discussed in Duke's letter to Region II dated March 8, 1974. A licensee representa-tive explained that both incidents apparently resulted from the LDST gas sample outlet line being improperly rcuted to the upstream side of the waste gas exhauster, which is norcally isolated.
A Station Modification Report has been sub=itted to relocate the sample line.
In the interim, the LDST sampling valves have been " red-tagged" closed.
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