IR 05000270/1973010
| ML19317D335 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 08/28/1973 |
| From: | Jape F, Murphy C, Whitt K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19317D327 | List: |
| References | |
| 50-270-73-10, NUDOCS 7911270558 | |
| Download: ML19317D335 (16) | |
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UNITED STATES
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ATOMIC ENERGY COMMISSION,
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DIRECTCfsATE OF REGL*LATCRY CPERATIC:IS
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RO Inspection Report No. 50-270/73-10 l
Licensee:
Duke Power Co:::pany Power Building 422 South Church Street Charlotte, North Carolina 28201 i
Facility Name: Oconee Unit 2 I
Docket No.:
50-270 License No.:
CPPR-34 Category :
A3/B1
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Location:
Seneca, South Carolina Type of License : B&W, PWR, 2568 Mw(t)
Type of Inspection:
Special, Announced (August 7-9, 1973)
l Routine, Unannounced (August 13-17, 1973)
Dates of Inspection: August 7-9, 1973, and August 13-17, 1973 Dates of Previous Inspection:
July 2-3, 1973, and July 17-20, 1973 i
Principal Inspector:
F. Jape, Reactor Inspector, Facilities Test
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and Startup Branch
l Accompanying Inspectors:
K. Whitt, Reactor Inspector Facilities Test and Startup Branch (August 7-9, 1973)
C. M. Campbell, Radiation Specialist i
Radiological and Environmental Protection
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Branch (August 14-16, 1973)
Other Accompanying Personnel:
None i
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~U Principal Inspector:
l F. Jape, Reactor IKspector, Facilities Test and Date
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l Startup Branch I
Reviewed by:,
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C. E. Murphy, Chilef / Facilities Test and Startup Branch 7 Date
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RO Rpt. No. 50-270/73-10-2-O
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Summarv of Findings
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I.
Enforcement Action A.
Violations The following violation is considered to be of Category II Severity:
Loss of Test Control Four accelerometers which were installed on the reactor coolant piping system to perform TP 200/36, " Loose Parts Monitoring Functional Test," had been relocated without the test coordinator's knowledge.
Performance of the test with the sensors in other than designated locations appears to be in violation of Criterion XI, "Tast Control,"
of Appendix B to 10 CFR 50.
(Details I, paragraph 2)
B.
Safety Items None
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II.
Licensee Action on Previously Identified Enforcement Matters A.
Violations Welding Program Deficiencies (RO:II Letter to DPC, dated March 8,1972, Item 5)
The licensee's report on welding deficiencies and documenta-tion has not yet been made available to RO for review.
This
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item remains open.
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B.
Safety Items
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There are no previously identified safety items.
III. New Unresolved Items
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73-10/1 Administrative Procedures
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A review of administrative procedures and instru. tions currently in effect revealed that three additional procedures were required in order to be in complete agreement with Reguia:ory Guide 1.33.
(Details I, para-
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graph 3)
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RO Rpt. No. 50-270/73-10-3-
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Status of Previously Reported Unresolved Itecs
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73-9/1 control Rod Drive Breaker Undervoltage Trip Assembly e
Deficiency
- Corrective actions described in the licensee's report, dated February 23, 1973, have been completed and the inspector has no further questions.
(Details I, para-graph 4)
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73-8/2 Valve Wall Thickness of valve 2-RV-67 Calculation of valve wall thickness of valve 2-RV-67 in accordance with the applicable codes remains to be resolved.
73-8/1 Body Wall Thickness of valves 2-51-244 and 2-51-245 Justification for body wall thickness of valves 2-51-244 and 2-51-245 being less than that permitted by RO letter, dated June 30, 1972, paragraph 3, remains to be resolved.
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73-1/1 Core Flooding System Testing Reouirement The results of TP 201/7, " Core Flooding System Flow Test," have been analyzed and approved by the licensee.
The inspector has no further questions on this item.
This item is resolved.
(Details I, paragraph 5)
V.
Unusual Occurrences None
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VI.
Other Significant Findings
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A.
Hot Functional Testing
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Hot functional testing (HFT) is currently at Phase II,
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" Hot Operations." There are seven phases in the HFT
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program.
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B.
Personnel Injury
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A DPC employee received first and second degree burns when a steam relief plug operated during HFT. No nuclear material as involved in th e accice...
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RO Rpt. No. 50-270/73-10-4-
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C.
Personnel Changes
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The following personnel changes were announced August 2,1973:
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1.
M. D. McIntosh was promoted to Assistant Plant Superintendent
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at DPC's McGuire Station.
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L. E. Schmid was promoted to Operating Engineer at the Oconee Station.
3.
T. L. McConnell was promoted to Assistant Operating Engineer at the Oconee Station.
4.
C. Yongue was promoted to Assistant Health Physics Supervisor (new position).
VII. Esnagement Inte rviev i
A management interview was held on August 17, 1973, with the following in attendance:
Duke Power Company (DPC)
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J. E. Smith - Plant Superintendent
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J. W. Cox - Assistant Plant Engineer T. L. Cotton - Junior Engineer The following items were discussed:
A.
Review of Administrative Procedures The inspector stated that he had reviewed the administra-tive procedures currently in effect with those described in Regulatory Guide 1.33; there are three procedures lacking.
The licensee's representative stated that these would be pre-pared by September 20, 1973.
(Details I, paragraph 3)
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B.
Previously Reported Unresolved Items The status of previously reported unresolved items, as 'escril1ed
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in Section IV of the Summary of Findings, was discussed.
(D-: ails
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I, paragraphs 4 and 5)
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C.
High Energy System Interim Measures The inspector stated that la had reviewed the status of the interim measures for Oconee 2, presented in 3CS Rep::t OS-73.2, j
" Analysis of Effects Resulting Froc Festulated Piping Breaks
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Outside Containment," dated April 25, 1973, and Supplement 1, (
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RO Rpt. No. 50-270/73-10-5-I dated June 22, 1973.
The design of all items is complete
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except for the main steam restraints.
(Details I, paragraph 6)
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D.
Initial Fuel Loading Procedure f
T' e inspector stated that he had discussed comments on OP 1502/4, h" Initial Fuel Loading " with the licensee's representative and that all have been resolved.
(Details I, paragraph 7)
E.
Witnessing Hot Functional Tests Performance of three HFT's was witnessed by the inspector.
1.
IP 330/3A, " Control Rod Drive - Rod Drop Time Test" 2.
TP 200/12A, "RC Pump Flow Test (HFT)"
3.
TP 200/36, " Loose Parts Monitoring Functional Test"
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There were no questions or deficiencies noted on IP 330/3A l
and TP 200/12A.
l A deficiency was noted bv the inspector during the performance
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of TP 200/36.
(Details 1, ptragraph 2)
F.
Test Equipment Control The inspector stated that he had reviewed the program for control of measuring and test equipment and had no comments or questions.
(Details I, paragraph 8)
G.
Process and Area Monitors Calibration of process and area monitor has not been completed.
The licensee's representative indicated that this work will be completed prior to initial fuel loading.
(Details II, paragraph 3)
H.
Verification of Adeotice Hood Air Flew The inspector commet::ed that the verification of adequate air flow for the sampling hood has not been completed.
The licensee's
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initial fuel loading.
(Details II, paragraph 4)
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Licensee's Program for Personnel Monitoring i
The inspector stated that he had reviewed the program for use and evaluation o! TLD's and had no coerent or questions regardins
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the program.
(Details II, paragraph 10)
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RO Rpt. No. 50-270/73-10-6-Os J.
Potential for Unscheduled Release of Radioactive Liquid
Waste e
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The inspector reviewed the licensee's progress regarding a'ction on the letter from R. C. DeYoung, L, to A. C. Thies, DPC, dated July 19, 1973.
(Details II, paragraph 13)
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RO Rpt. No. 50-270/73-10 I-1
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Prepared By:
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DETAILS I
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F. Jape, Resctor Inspector Date Facilities Test and Startup Branch
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cYlbS K. W. Whitt, Reactor Date Inspector, Facilities Test and Startup Branch Dates of Inspection: August 7-9, 13-15 and 17, 1973 Reviewed By: M v
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.F';t,9 7f C. E. Mur.phy, A ief
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Facilities Test an Startup Branch 1.
Individuals Contacted Duke Power Company (DPC)
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J. E. Smith - Plant Superintendent J. W. Hampton - Assistant Plant Superintendent
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R. M. Koehler - Technical Support Engineer 0. S. Bradham - Instrument and Control Engineer
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G. W. Cage - Assistant Operating Engineer J. W. Cox - Assistant Plant Engineer R. C. Collins - Performance Engineer D. J. Rains - Assistant Plant Engineer R. J. Brackett - Junior Engineer W. A. Brown - Chemist T. L. Cotton - Junior Engineer g O. A. Farabee - Junior Engineer G. G. Reynolds - Junior Engineer
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R. T. Bond - Junior Engineer S. A. Holland - Assistant Operating Engineer T. M. McConnell - Assistant Operating Engineer B. Moore - Junior Engineer D. Rogers - Junior Engineer
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'R0 Rpt. No. 50-270/73-10 I-2 O
2.
Witnessing Hot Functional Tests The inspector witnessed performance of the following hot functional tests (HFT):
I IP'330/3A, " Control Rod Drive - Rod Droptime Test" a.
b.
TP 200/12A, "RC Piup Flow Test (HFT)"
IP 200/36, " Loose Parts Monitoring Functional Test" c.
There were no questions or deficiencies noted on IP 330/3A and TP 200/12A.
The acceptance criteria on these tests were satisfied.
A deficiency was noted by the inspector during the performance of TP 200/36.
The test was run with four of the eleven sensors in a location different from that specified in the test procedure.
The table below shows the sensor location as found and as specified.in j
the test procedure:
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Sensor Location i
Sensor No.
Actual As Specified by TP
l Incore Guide Tube 41 Incore Guide Tube 41
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Incore Guide Tube 48 Incore Guide Tube 48
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Incore Guide Tube 1 Incore Guide Tube 1 j
CRD 67 Incore Guide Tube 34 j
CRD 63 Incore Guide Tube 52
SG 2A Hand Hole SG 2A Hand Hole
SG 2A Tube Sheet Vent SG 2A Tube Sheet Vent
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SG 23 Hand Hole SG 2B Hand Hole i
SG 2B Tube Sheet Vent SG 2B Tube Sheet Vent
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The location of four sensors had been changed about a week prior to
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performing the test, and after the initial verification of the sensor location by the test coordinator, to monitor a condition on selected control rod drives (CRD).
The inspector stated that relocation of sensors without the test coordinator being aware of the change appeared to be in violation of Criterion X, " Test Control," of Appendix B to 10 CFR 50.
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RO Rpt. No. 50-270/73-10 I-3 b>
3.
Review of the Administrative Procedures for Implementing the Quality
Assurance Program i
The inspector reviewsi administrative instructions and procedures which have been prepared by the licensee for implementation of the quality assurance program.
The findings of this review are summarized below:
a.
Security and Visitor Control
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A memorandum was issued November 11, 1971, delineating the procedure to be used for visitor control.
The procedure has been in effect since that date and the inspector has no questions regarding its use and effectiveness.
b.
Authorities and Responsibilities for Safe Operation and Shutdown The licensee has provided Administrative Procedures No. 3, '.' Actions To Be Taken In Case of Exceeding Limits," No. 4, " Duties of the Control Operator on the Control Board," and No. 7, " Reasons for Notifying the Operating Engineer or Superintendent." The inspector reviewed these three procedures and had no question or comment.
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c.
Equipment Control (e.g., Locking and Tagging)
Administrative Procedure No. 2, " Tagging, Delineation, and Safety,"
has been provided by the licensee.
This procedure was reviewed
by the inspector and there were no questions or comments.
d.
Procedure Adherence and Temporarv Change Method Administrative Procedure No. 8, " Procedures," has been provided
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by the licensee to require adherence to procedures.
Instructions
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for making temporary changes are also covered.
The inspector had no comment or question regarding this procedure.
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e.
Procedure Review and Approval Section 4.4, " Administrative Instructions for Permanent Station Procedures," of the Administrative Policy Manual for Operational Quality Assurance of Nuclear Stations (APM/NS) provides the necessary instructions for procedure review and approval.
The inspector had no comment or questions on this item.
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RO Rpt. No. 50-270/73-10 I-4 i
f.
Schedule for Surveillance Tests and Calibration The licensee has a program for surveillance testing and calibra-
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The program is designed to ensure all tests required by
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tee.hnical specifications are assigned to a component of the station organization.
Periodic tests and instrument procedures listed in the master index, which are not a part of the technical specifications, are also assigned to a group for completion.
The current status of surveillance tests and calibrations was recently audited by the QA group and the inspector reviewed these audit reports.
The findings indicated that all tests are being done on schedule.
The inspector had no further questions on this item.
g.
Shift and Relief Turnover A written procedure has not been prepared as yet.
The licensee's
representative has stated that an administrative procedure will be issued by September 20, 1973.
This item will be carried as UN 73-9/2 pending final resolution.
h.
Log Entries and Record Retention The licensee has issued Standing Orders 8, " Shift Supervisor's Log," and 9, " Reactor Operation Log."
These instructions were reviewed by the inspector.
There were no comments or questions regarding these itecs.
1.
Access to Containment A specific, written procedure for this item has not been prepared as yet. Access to the containment is under the control of the shift supervisor.
T.'e containment doors are locked and the shift supervisor has the key.
The licensee's representative has stated that an administrative procedure will be prepared for this item.
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Issuance is expected by September 20, 1973.
This item will be carried as UN 73-9/2 pending final resolution.
j.
Bypass of Safety Functions and Jumper Control The licensee has provided MP~1400/20, " Electrical Interlock and Circuit By-Pass Procedure." This maintenance procedure specifies tiie details and requirements for bypassing or lifting leads for all safety related equipment.
The inspector had no comment or question regarding this iter.
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RO Rpt. No. 50-270/73-10 I-5
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Recall of Standby Personnel to Plant i
A formal, written procedure for this item has not been prepared as yet.
The licensee's representative has indicated that such a procedure will be prepared and issued by September 20, 1973.
This item will be carried as UN 73-9/2 pending final resolution.
4.
Control Rod Drive Breaker Undervoltage Trip Assecbly Deficiency During a previous inspection,1/ it was reported that the field change to install a 5 amp fuse in each of the four reactor protection system channels had not been completed.
A current review of this item re-veals that this work is now complete.
The inspector reviewed Field Change 113 and the accompanying installation procedure.
There were no questions or comments.
This previously identified unresolved item, No. 73-9/1, is resolved.
5.
TP 201/7, " Core Flooding System Flow Test" During a previous inspection,2/ it was reported that the licensee's analysis of the test data was not complete.
The licensee's analysis has been completed and the inspector has no further questions or comments.
The licensee has determined that the core flood system will functionally deliver water to the reactor vessel and that the observed piping frictional losses are consistent with calculated ------
piping frictional losses for the installed core flooding system.
This previously identified unresolved item, No. 73-1/1, is resolved.
i 6.
Protective Interim Measures for High Energy Systems MDS Report No. 05-73.2, " Analysis of Effects Resulting from Postulated Piping Breaks Outside Containment for Oconee Nuclear Station, Units 1, 2 & 3," dated April 25, 1973, presents interim measures to be
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taken prior to the completion of design changes which are described
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The schedule for completion of proposed station
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modifications was reviewed.
The design of all ite=s is complete except for the main steam line restraints.
Materials delivery has
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begun and no delays are anticipated.
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1/ RO Inspection Report No. 50-270/73-9, Details I, paragraph 5.
2/ RO Inspection Report No. 50-270/73-9, Details I, par::::ph
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RO Rpt. No. 50-270/73-10 I-6
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The interim Jurveillance r,s a r me ' '. described in Section 4.1 of the report, are to be implemented foiAowing issuance of an operating license and initial criticality.
1he licensee has provided PT 250/11,
'9Kain Steam, Auxiliary Steam, Condensate and Feedwater Line Inspection,"
to describe and record the interim surveillance measures.
The inspector reviewsd th:s PT and found that it contained all of the interim measures rec uirements.
There were no questions or comments on this item.
7.
OP 1502/4, " Initial Fuel Loading" e
The inspector reviewed the initial fuel loading procedure using as guidance the Oconee Technical Specifications, FSAR manuals and the AEC's Guide for the Planning of Initial Startup Programs.
Comments and the licensee's response are listed below.
All connents have been resolved and the inspector has no further questions on this item, a.
Inspector's Comment - In item 2.10, it is stated that the SRO in charge of fuel handling operations will be at the site.
Shouldn't his location be more definitive?
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Licensee's Respense - This item will be changed to state the SRO
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shall be located within the areas concerned with fuel loading
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activities.
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Inspector's Comment - Item 2.13 states that the fuel assembly grapple may ha released after proper seating has been verified.
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Shouldn't a stable count rate also be observed before a fuel assembly is released?
Licensee's Response - This item will be revised to require i
observation of a stable count rate prior to releasing the fuel i
assembly grapple.
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Inspector's Co= ment - The Emergency Procedure, EP 1800/18, referred to in item 2.21 is for Oconee 1.
Does this same l
procedure apply to Oconee 2?
Licensee's Response - EP 1800/18, " Emergency Procedure," applies
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The typographical error will be
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RO Rpt. No. 50-270/73-10 I-7 I
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With the resolution of the above comments, the inspector concluded that OP 1502/4 is in agreement with applicable guides.
e 8.
Test Equipment Control A review of the licensee's program for control of measuring and test equipment was completed by the inspector.
The inspector found the program to be in agreement with the requirements of Criterion XII, " Control of Measuring and Test Equipment," of Appendix B to 10 CFR 50, and with DPC's APM/NS, Section 2.3.
The inspector's comments have been resolved.
9.
System Hydro Testing and Cleanliness The inspector reviewed the records for hydro tests and cleanliness of the following:
a.
Main Steam System Hydro test performed as described in TP 270/2, "SG Hydro Test."
System cleanliness was visually checked by a worker crawling through the lines.
b.
Reactor Vessel and Internal Components System was cleaned as described in TP 200/16, "RC System Final Cleaning Procedure." The reactor vessel was hydrostatically
tested / as prescribed in TP 200/3C, "RC System Hydro Test."
There were no deficiencies noted from the review of these records.
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10.
Review of Preoperational Tests by RO Current status of RO:II's review of preoperati.onal testing is as follows:
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Test Category Tests Reviewed Test Results Reviewed No.
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l 3/ 1 tnapec:ien Repec: :L. 30-270/73-6, Details I, paragraph 14.
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RO Rp t. No. 50-270/73-10 II-1 i
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DETAILS II Prepared by:
C. M. Campbell, Radiation Specialist Date Radiological and Environmental Protection Branch
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Dates of Inspection: August 14-16, 1973 bLh/ Y biY R/ ^} 7)
Reviewed by:
KT. Sut'herland, Acting Chief Mate (
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Radiological and Environmental Protection Branch 1.
Individuals Contacted (All Duke Power)
i J. E. Smith - Plant Superintendent R. M. Koehler - Technical Support Engineer C. T. Yongue - Assistant Health Physics Supervisor
G. Cage - Assistant Operational Engineer R. Leonard - Labman J. Itin - Labman 2.
Organizational Changes
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and filled in the 'dealth Physics Organization.
The position title
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is Assistant Health Physics Supervisor. -This position has been
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filled by the promotion of C. Yongue from Health Physics Technician.
3.
Process and Area Monitoring System l
Installation of area and process monitors has been completed.
Calibration of these units is in process.
The inspector was
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informed that calibration of all but two of the area monitors (2RIA 16, 17) has been completed and seven of the thirteen process monitors have been calibrated. Management plans to i
complete calibration at the remaining units prior to fuel
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l loading (as reported in R0 Report 50-270/73-6).
4.
Verification of Adecuate Hood Flow in the Unit 2 Samoling Room This verification had been pending completion of modifications to the unit 2 sampling room as discussed in RO Report 50-270/73-6.
A licensee representative informed the inspector that the sampling room modifications have been completed and that the verification
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of hood flow adequacy would be done in the next two weeks. Manage-cent agreed with this statenent.
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RO Rpt. No. 50-270/73-10 II-2 (-
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5.
Minimization of Halogen Losses in Outside Sample Delivery Line
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The inspector observed that the insulation of the sample line had not yet been done.
A licensee representative stated that this would.be completed prior to fuel loadiag.
Management agreed.
6.
Approved Radiochemistry Procedure for Gamma Spectrometry A licensee representative told the inspector that he would check into this and see if approval of this procedure had been completed.
This item had been discussed in R0 Report No. 50-270/73-6.
7.
Status of Biological Shielding Survey The inspector was informed by licensee representatives that the background survey was in progress on August 16-17, 1973. A licensee representative stated that the in-plant portion of the survey was completed on August 17, 1973, and the remaining portion of the survey will be completed in the next few days.
Discussions with a licensee representative and review of the existing Biological Shield Survey Procedure showed that the procedure has not yet received final approval and is being held pending completion of changes to the Unit 1 procedure.
N 8.
Operating Procedures for the Resin Transfer System The offsite portion of the resin transfer system is common to Units 1 and 2 and therefore the offsite transfer procedures for both units will be identical. A licensee representative stated that the procedures for resin transfer from the individual demineralizers to the spent resin storage tank will be included in resin replacement procedures for each system. The inspector observed that these procedures are on the list of procedures to be written (OP/2/A 1104/22, 23 & 24).
9.
Operation and Calibration Precedures for Beckman Liquid Scintillation System
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The status of these procedures is essentially as reported in RO Report 50-270/73-6. A licensee representative stated that vendor supplied procedures are currently being used.
10. Quality Assurance Methods in TLD Program Dis'cussion w'ith a licensee representative showed that they have submitted spiked TLD's, through the normal submission channels, i
- the cer-ercial servi:: er-2nt:stien for evaluatien.
He further
- a;2d cho eney plan ;
- cea;inue tais practice periccic
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RO Rpt. No. 50-270/73-10 II-3 11. Procedures The inspector examined the Reactor Building Purge System Functional and Operational Test (TP/2/A/161/3) and the High Efficiency Particulate Air Filter Test Procedure (PT/1/A/161/4) and had no comments.
12. Health Physics Personnel A licensee representative stated that two additional laboratory assistants have been hired and that health physics personnel are no longer working shifts but are available en an on-call basis.
13. Review of Waste Overflow to Other Than a Controlled Water Pathway to the Environs Review of Station Problem Reports showed that the licensee has initiated action to fullfill the review, requested by AEC/ DOL, of the possibility of releasing radioactive liquid through an uncontrolled water pathway.
Station Problem Report No. 211 recommended that the overflow line from each Borated Water Storage Tank be piped over to the nearby pipe trenches that drain to the Low Activity Waste Tank.
The S.R.P. also referenced the (3 request of R. C. DeYoung, AEC/ DOL, to review possible liquid releases
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to uncontrolled water pathways.
The station problem report was reviewed and approved on August 7,1973, by the Station Review
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Committee (SRC) as shown in SRC minutes numbered 73-85 which scare reviewed by the inspector.
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