ML19322A614
| ML19322A614 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 03/11/1971 |
| From: | Murphy C, Seidle W US ATOMIC ENERGY COMMISSION (AEC) |
| To: | |
| Shared Package | |
| ML19322A611 | List: |
| References | |
| 50-269-71-02, 50-269-71-2, NUDOCS 7911210688 | |
| Download: ML19322A614 (14) | |
Text
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U. S. ATOMIC ENERGY C0K4ISSION REGION II DIVISION OF COMPLIANCE Report of Inspection CO Report No. 50-269/71-2 Licensee:
Duke Power Company Oconee 1 License No. CPPR-33 Category B Dates of Inspection:
January 25, 1971 Feb ruary 10-12, 1971 Dates of Previous Inspection:
January 5-8, 1971 Inspected By:
_11 P 7/
C. Il. librpig % actor Inspector (Operations)
~/DaEe '
Reviewed By:
W. C. Seid#e, Senior Reactor Inspector Date Proprietary Information:
None SCOPE A routine, announced inspection was made of the 2568 N(t) pressurized water reactor under construction near Seneca, South Carolina, known as Oconee Station No. 1.
Purposes of the inspection were :
1.
To decermine the construction status and significant changes to the schedule dates.
2.
To review the outstanding items remaining to be completed at the f acility.
3.
To review the electrical and instru=entation installations with DRL, DRS, and DR personnel.
4.
To review the test program.
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j911210 b N
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C0 Rpt. No. 50-269/71-2,
SUMMARY
Safety Items - None Nonconformance Items - None Unusual Occurrences - None Status of Previously Reported Problems -
1.
The licensee has revised the FSAR to show the station batteries in the new location.
(See Section F and Management Interview.)
2.
The cleaning procedures for the reactor coolant piping and equipment has been revised to conform to the FSAR.
(See cection G and Manage-ment Interview.)
3.
The licensee is presently reviewing and correcting the deficiencies in the electrical and instrumentation QA documentation.
(See Section F.)
Other Significant Items - S. Hanauer, DR, V. A. Moore, DRS, A. Schwencer, DRL, O. D. Parr, DRL, and F. Rosa, DRS, visited the site to review the electrical and instrumentation installation on February 11 and 12,1971.
This review did not reveal any items of major significance.
(See Section F.)
Outstanding Items - See Exhibit A for current status of outstanding items.
3 Management Interview - The management interview was held on February 12, 1971, and was attended by Smith, Hampton, Owen and Wells.
1.
Owen stated that the ventilation system for the Keowee plant battery system would be modified to ensure adequate air supply and exhaust in ';oth battery areas.
(See Section F.)
2.
Smith stated thtt procedures would be developed to require periodic checking of the blocking diodes in the switchyard d.c. system.
(See Section F.)
3.
Owen and Smith sta' ed that the temporary steam line above the 4 kv switchgear would be removed, the manual valve closed and its handwheel removed. A blank flange would be installed at the valve discharge.
(See Section F.)
4.
The inspector. reviewed the problems associated with the relocation of the station batteries. Owen advised the inspector that a protective
Ih CO Rp t. No. 50-269/71-2.
i housing would be installed around the station power batteries. The instrument air line in the control power battery r om will Se removed and the floor drain line for the elevation above
- un battery room will have a guard installed to prevent water from spill ng onto the battery.
Owen stated that the licensee's response to the Ci j/ would describe these changes.
(See Section F.)
5.
The containment leak rate test-procedure specifies that the leak rate will be determined both by the absolute method and the reference vessel method at the maximum accident pressure and at 50% of this pressure.
The accuracy of the tests is to be verif *ed by introducing a controlled leak.af ter the completion of the test at 50% pressure. The inspector advised Smith that consideration should be given to including the con-I trolled. leak rate test at the conclusion of the 100% pressure test since the accuracy of the leak rate measurement at the full accident pressure must be verified. Smith stated that consideration would be given to the' inspector's comments.
(See Section G.)
6.
In. response to the in3pector's question, Smith stated that the test
)
procedures would be revised to reflect the. latest revisions to the FSAR and the Technical Specifications.
(See Section G.)
7.
The elevator in the auxiliary building. opens into the penetration Since this room must.be maintained at.a negative pressure, the
. room.
inspector asked if the effect of the elevator door remaining open had l,
been. considered. Owen stated that the door details would be reviewed to determine the adequacy of the seals. Smith said that he would verify that the doors would close auteret lea 11y at this level.
8.
The need for separation of redue.da:tt circuits in the control boards was. discussed. Owen stated that the licensee would establish criteria for separation of safety-related circuits and issue a report to DRL.
j Those. wires in redundant circuits which failed tc meet the criteria would be rerouted.
(See Section F.)
4 9.
Wells stated that the cable trenches in the powerhouse and switchyard area would be cleaned of debris and mud.
4 10.
In. response to the inspector's question, Wells stated that the instru-
, meet air line attached to the cable tray supports in the auxiliary 4
building would be removed.
11.
The inspector. advised Smith and Hampton that.the procedures for the hydrostatic testing did not. provide for repairing leaks.and ratesting.
In addition, no acceptance criteria were given nor were the individual 1/CDN issued on January ~29, 1971.
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00 Rpt. No. 50-269/71-2 leak rates determined. This would not appear to permit adequate evaluation of the tests. Smith stated that consideration would be given to changing the procedures.
12.
Smith streed that operating procedures, emergency procedures and health physica procedures vould be made available to the inspector.
- 13. Wells advised the inspector that. the defective section of feedvater piping at the steam generator 1A ring header would be replaced.
- 14. The inspector advised Wells that during a tour of the reactor building he had observed a bundle of stainless steel velding roi laying on a scaffold near steam generator 1A.
This rod, which had no identifica-tion as to source, was in an area where velding of stainless pipe was in progress. Uells stated that he uould folicw up on this item and instruct his men to be on watch for improperly handled rods.
15.
The inspector stated that he had observed an unlocked door on steam generator 1B clean room. The door was not guarded nor was there a notice restricting admission.
Smith stated that he would fo11cw up and correct this item.
- 16. The inspector advised Smith that he had reviewed Procedure TP 20016, 3.4, dated December 30, 1970, which described the cleaning of the steam generator tubes. The procedure was considered to be accep tab le.
DETAILS A.
Persons Contacted Duke Power Cetmanr (Duke)
R. L. Dick - Manager of Construction J. C. Rogers - Project Engineer D. G. 3esn - Assistant Project Engineer J. R. Uells - Principal Field Engineer G. L. Hunnicutt - Senior Field Engineer M. E. Blaisdell - Field Engi 9er, Welding G.11. Grier - Field Engineer, NDT C..B. Aycock - Field Engineer, Electrical
.J. C.. Smith - Plant Superintendent J. W. Hampton - Assistant Superintendent
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C0 Rpt. No. 50-269/71-2 B.
Administration and Organization There have been no significant changes to the licensee's staff since 3
the previous inspection.
C.
Quality Assurance The licensee has instituted a program for training and upgrading the NDT technicians. The technicians are being given 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> of formal instruction in dye penetrant testing. Those that complete the course and pass a written examination will be qualified as SNT, Level II technicians. After the completion of this course, the licensee plans to conduct similar courses in MT and RT.
At present, sixteen men have been qualified to Level II in dye ~ penetrant testing.
D.
Construction Progress 1.
Instellation of the reactor vessel internals is underway.
2.
Seismic braces are being installed on the primary system piping and the steam generators.
3.
Testing of the piping, electrical and instrumentation systems is in progress.
4.
Approximately 70% of the instrument and control cable and 92% of the power cable have been installed.
E.
Construction Schedule 1.
The hydrostatic test of the reactor coolant system is scheduled for mid-March 1971.
2.
The containment proof test is scheduled for the last week of March 1971.
3.
The start of the hot functional test is now planned for April 1971.
F.
Electrical and Instrumentation 1.
DRL Site Visit S. Hanauer, DR, V. A. Moore, DRS, A. Schwencer, DRS, O. D. Parr, DRL, and F. Rosa, DRL, visited the site to review the electrical and instrumentation installation on February 11 and 12,1971.
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CD Rpt. No. 50-269/71-2 The Compliance inspector participated in this review. At the con-clusion of the review, a meeting was held with the licensee's personnel and the following items were discussed.
a.
Keowee Hydro Plant - The ventilation system for the two battery rooms appears to ventilate only one room.
Owen stated that the system would be revised to incorporate a separate ventilation system for the second battery room.
b.
230 kv Switchyard - Two batteries provide power for operating the power circuit breakers in the switchyard. Blocking diodes are used to provide isolation between the two batteries. The licensee has not provided a method for monitoring the diodes for possible failure.
Smith stated that procedures would be developed for the periodic testing of the diodes. This item will be reviewed in the technical specification meetings.
c.
4160 Volt Switchgear - A steam line to be used in the alkaline wash of the secondary systems passes in close proximity to the Unit 1 engineered safety system 4160 volt switchgear.
Owen stated that this was a temporary line and that the pipe would be removed and its supply valve closed and capped. As a final safety measure, Smith stated that the valve operator would be removed, d.
Battery Room - The control power batteries were relocated from the turbine building mezzanine floor to the auxiliary building.
The new location contained an instrument air line and a floor drain line serving that elevation above the batteries.
Owen stated that the air line would be removed and the drain line would have a guard installed to prevent spills onto the batteries. The 7SAR has been revised to show the new battery locations and the licensee's response to the CDN / will 1
include the corrective action taken.
e.
Control Room - Wiring to switches that provide for manual actuation of redundant engineered safety feature pumps and valves appeared to be bundled together.
!1ylie stated that the licensee would establish c51teria for the separation of wiring for redundant devices. The designs k
1/CDNissuedJanuary 29, 1971.
('T C0 Rpt. No. 50-269/71-2 for these devices would be reviewed and those that did not have proper separation would be rewired to provide separation.
The results of this review will be submitted to DRL.
f.
Instruments Inside Containment - Transducers for the primary system flows and the primary system pressure channels were mounted side by side.
Owen stated that the installation would be reviewed to assure separation of redundant systers.
2.
Electrical and Instrumentation Records Wylie advised the inspector that the licensee's review of the electrical and instrumentation documentation was nearing com-pletion. He stated that the deficiencies which had been pre-viously noted by the inspector 1/ were being corrected and that more thorough reviews would be made in the future to ensure that the documentation was accurate and complete.
G.
Test and Operation
- 1. - Reactor Coolant System Cleaning Procedure The inspector reviewed Reactor Coolant. System Cleaning Pro-cedure TP 1A 20016 with Smith and Hampton. This procedure, which replaced Field Installation Procedure 15, presents in detail the methods for cleaning, inspecting and testing to assure the cleanliness of the reactor coolant system. The inspector advised Smith that no deficiencies had been noted in this pro-cedure. -Enclosure 13.4, dated December 30, 1970, of the procedure gave detailed requirements for cleaning the steam generator tubes using felt plugs. This enclosure, if followed, would provide adequate assurance that the steam generator tubes were properly cleaned. The inspec*or plans no further action on this item at the present time.
2.
Instrument-Test Procedures The inspector advised Smith that the instrument test procedures shoald state which sections, if any, could be accomplished with the plant operating. Smith stated that all instrument procedures would be reviewed to determine which could be completed with the 1/C0 Report No. 50-269/70-12.
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I' CO Rpt. No. 50-269/71-2,
plant operating and these procedures or procedure sections would be identified.- Other instrument procedures would only be used during plant shutdown.
3.
Containment Leak Rate Ifeasurements The inspector discussed Containment Leak Rate Test Procedure TP 1A 150 3 in detail with Smith and Hampton. This procedure specifies that the leak rate would be calculated by the absolute method and by the reference vessel method. The data for these calculations are to be taken with the containment pressurized to the calculated accident pressure and to 50% of this pressure.
Since. essentially the same data is used for both calculational methods, a controlled leak is to be introduced to verify the i
sensitivity of the instruments to a known leak and to verify the accuracy of the data used in the leak rate calculations. The licensee has proposed that the controlled leak rate test be i
performed at 50% of calculated accident pressure. The inspector advised Smith that he should consider running the controlled leak rate test at 100% pressure since confirmation of the leak rate test at this pressure is of more value than at 50% pressure.
Smith advised the inspector that this matter would be considered.
4.
Test Procedure Review The. inspector gave Smith and Hampton comments on the following procedures :
Number Title TP 1A 150 4 Reactor Building Hatches Leak Tests TP 1A 170 2 Auxiliary Building Vent System Functional Opera-tional Test TP 1A 2001:
Reactor Internals Vent Valve Inspection Test TP 1A 200 3 Reactor System Hydro Test TP 1A 200 1/A Reactor Flow Instrument Control Pre-op Calibration TP 1B 202.lA Reactor Coolant Pump Seal Supply Return Temperature Pre-op Calibration TP 1B 202 1E Letdown Storage Tank Pressure Instrument TP 1B 202 1F Letdown Storage Tank Level Instrument TP 1B 202 1G Letdown Storage Tank Temperature Instrument TP 1B 202 II Letdown System Temperature Instrument TP 1B 202 IJ
' Letdown System Pressure Instrument TP 1B 202 1K Hydrogen Makery System Pre-op TP 1A 202 2 HP System Hydro Test TP 1A 202 5 HP System Engineered Safeguards Test TP IB 203 1A Borated Water Storage System Level Instrument
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CO Rpt. No. 50-269/71-2 g3 TP 1B 203 LB Borated Water Storage Tank Temperature Instrument TP 1A 203 4.
LP Injection System Hydrostatic Test TP 1A 203 6.
LP Injection System ES Test TP 1A 120 3 Fuel Handling System. Integrated Functional Test TP 1B 150 1A Reactor Building Humidity Measurements TP IB 150 1C Reactor Building Absolute Nkasurements TP 1A 160 2.
Reactor Building Coolers Functional Test TP 1B 161 1.
Reactor Building Vent System Functional Test TP 1B 161 4.
. Hydrogen Purge Test EP 1 1800 18 Emergency Procedure - Emergency Plan Hampton stated that the inspector's comments would be reviewed and if any were not incorporated into the procedures, the inspector would be advised.
5.
FSAR and Technical Specification Changes The inspector pointed out to Smith and.Hampton that the test pro-cedures reviewed to date contained. data which were in the Technical Specifications.
Specific. examples were the reactor coolant system heatup rate, the nil ductility transition. temperatures and contain-ment accident. pressures. Since.the FSAR.and the Technical Specifi-cations.were being revised, the. test. procedures should be reviewed
.and corrected as required. Smith and Hampton stated that this would be done.
6.
Outstanding Items List The inspector reviewed the outstanding items list with Smith and Hampton. None of the items listed has been resolved except item 42, Cleaning Reactor Coolant System Piping and Equipment.
i Attachment :
Exhibit A i
.I
l d
l L"CENSEE.
Duke Power Ccmpany (3
FACILITY Oconee Station No. 1
'f DOCKET 8: LICENSE NOS.
50-269, CPPR-33 REACTOR OUTSTANDING ITD1S IDENTIFIED ITEM CI,0 SED 1.
68-2, 3/5/68, Concrete test cylinder breaks below specs
~
.68-3,'D.5.,
j E
6/19/68 l 2.
68-3,6/19/68, Unauthorized revision to Cadweld specifications 68-4, Simmary, E
9/25/69 3.
68-3,6/19/68, Failure to provide concrete inspector 68 h, Simmary, E
9/25/69 h.
68-h,9/25/68 Failure to properly test Ct..'. veld splices 69-1, Summary, i
E 1/6/69 5.
69-8,9/9/69, Failure to properly qualify veld procedures 69-9,G,11/3/69 l
)'..
6.
69-8, 9/9/69, Failure to properly qualify veldors 69-9,G,11/3/69 E
7 IEB,h/11/69 Procedure for repair of arc strikes not available 70-5, Su= mary, 4/27/70 8.
CDN,1/8/70 NLT of core flooding valves Memo, VCS to HQ, 2/2/70 9
70-1,1/6/70, Welding and NDT deficiencies, CDN issued Memo, WCS to HQ, E
3/26/70*
10.
Bingham 69-1, Main coolant pump discrepancies
,Idemo, WCS' to HQ, 12/9/69, E h/21/70 11.
70-h,h/27/70, Lov strength concrete Memo, WCS to HQ, NC 8/7/70 12.
IEB, 5/1/70 Pressure vessel safe ends Memo, WCS to HQ, 8/5/70 13 70 6, 5/25/70, Tenden stressing discrepancies Memo, WCS to HQ, E
'v 8/7/70 M.' 70-8, 8/3/70, Tendons and stress gages Memo, WCS to HQ, E
10/8/70
'15 8,9/1/70,-
Fissures in primary coolant pipe cladding FSAR, Amend.24, E
12/17/70 16.
IEB, 9/11/70,
a.
Determination of safety system response to axial E
power imbalances b.
Availability of in-core detectors F - ID.ETI/IED Column:. S - safety item; NC - noncompliance or nonconformance ite=: UM - unresolveT item: IN - inquTry itom; IEB - Reactor Insnection and EnTErccmont tranch requeliC;' O - other source of iderbMricatibn A (briefly specify) 1 of 5 '
rum _
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LICalSEE Duke Power Company j
l (N FACILITY Oconee Station No. l' o
f DOCKET & LICBISE NOS. 50-269, CPPR-33 l
REACTOR OUTSTANDING ITB4S IDENTIFIED ITEM CLOSED o
c.
Measurements of flow and temperature during initial operation d.
Verification of bypass flow e.
Verification of axial peak effects on DNER f.
Data during startup for single loop, two pump l
operations g.
Inspection of reactor internals after completion I
of preoperauional tests I
h.
Field test of steam generator
- i. Low strength concrete and omitted tendons Memo, WCS to HQ, 10/8/70
,70-12, Summary
- j. Penetration roem valves 12/1/70 -
k.
Strain gauge failures Memo, WCS to HQ, 10/8/70 1.
HP and LP injection system startup times m.
Core flooding tank MO valve n.
Reactor building spray pump performance o.
Condenser cooling water crossover header valve t
p.
Spent fuel accident filters
.b
.{
J q.
Administrative control of MCP startup r.
Flov tests per 200/12 and 200/13 s.
Flev distribution chart F ~ IDEI;TIFIED Column: S - safety item; NC - noncompliance or nonconformance item; UN - unresolvei item; IN - inqul'ry item; IEB - Reactor Inspection and EnT6rcement Eranch requesE; O - other source of identification N
(briefly specify).
pa 2 of 5_
LICENSEE Duke Power Company l
FACILITY Oconee Station No. 1.
l DOCKET & LICFJTSE NOS. 50-269, CFPR-33 l
l REACTOR OUTSTANDING ITEMS i
IDENTIFIED ITEM CLOSED r
]17 70-2, 2/19/70, Vendor NIff records for safeguards systems cables 70-11, F, l
g 10/26/70 l 18.
70-4, 3/23/70, Verification of separation of transducer tubing b
19 70-8,8/3/70, Control rod drive guide bushings and torque tubes E
20.
70-8, 8/3/70, Completion of HP facilities E
/
21.
70-8,8/3/70, completion of HP procedures E
l 22.
70-8,8/3/70, completion of'HP personnel training 70-12, Summary E
12/1/70 23.
70-8, 8/3/70, Crane load test 71-1, 1/4/71 E
2h.
70-8,8/3/70, Verify that test procedures are properly revised'and E
approved when changes are required 25 70-8, 8/3/70, verify that analysis of containment is made FSAR, Amend. 24 E
26.
70-8, 8/3/70, Adei;uate fuel handling procedures 27 70-8, 8/3/70, Main steam pipe hangers E
28.
70-9,9/1/70, Steam generator skirt adapter indications E
29 70-9,9/1/70, HP injection pump QC records 70-11, C, g
10/26/70 30.
70-9,9/1/70, Basis for particle size in flusiting procedures 70-11, G,
.y U.N 10/26/70 c) 31.
70-9,9/1/70, Protection of instrumentation during hydro test E
d 32.
70-10, 9/28/70, Fuel transfer tube expansion joint replacement E
- 33. 70-10; 9/28/70, Routing of cables exterior to cable trays Memo, WCS to HQ R
1/18/71-F - IDENTI?IED Column: S - safety item; NC - noncompliance or nonconformance i item; UN - unresolveE item; IN - inqui7y item; IEB - Reactor Inspection and EnTorcement Branch reque3T; O - other source of identification 3
(briefly specify)
,"w 3 of 5 '.
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I l
l LICENSEE Duke Power Company (M.
FACILITY Oconee Station No. 1 j
I DOCIGT & LICENSE NOS.
50-269, CPPR-33 I
REACTOR OUTSTANDING ITEMS _
i l
IDENTIFIED ITEM' CLOSED i 34. DEL Rpt. No. 1, Installation of additional environmental monitoring 7/2h/70, E equipment e
j 35 DRL Rpt. No. 1, Vent valve replacement test j
7/2h/70, E
- 36. DRL Ept. No. 1, Strong motion accelerometer installation 7/2h/70, E -
i 37 DEL Rpt. No. 1, Penetration roan flow indication and adjustment i
{
7/2h/70, E l 38. DRL Rpt. No. 1, Instrumentation bypass keys Tech Specs Change i
7/2h/70, E 12/70 l 39 DRL Ept. No. 3, Internals vibration test 9/15/70, E 40.
DRL Rpt. No. 3, Core flooding tank valves 9/15/70, E h1 70-10,9/28/70, Hydrostatic t1st pressures 71-1, 1/4/71 E
h2.
70-11, 10/26/70,Cleaning reactor coolant system piping and equipment 71-2, 1/25/71 E
h3.
70-11,10/26/TO,Sens).tized stainless steel in reactor coolant pump g
discharge piping 71-1, 1/4/71 44.
IEB, 12/22/70 Reactor coolant pump tes ts 45.
IE3, 10/30/70 Safety inj ection system testing 46.
70-12, 12/1/70 Vibration testing - equipment and piping l 47.
70-12, 12/1/70 Location of station batteries E
- f 48.
70-12,12/1/70 Nuclear instrumentation vendor tests i
.NC, 49.
70-12, 12/1/70 Electrical QC data packages E
s 7 r IDEUTIIIED Column:
NC - noncompliance or nonconformance 3 - safety item; iry item; IEB - Reactor Inspection item: UN - unresolveii item:
IN - inqu and 7.nTerecment I; ranch request; ~O - other source of identification 3 (briefly speci.fy)
[
4 og 5
,.T
.a DukePbwerCompany LICENSEE f~N 4
FACILITY Oconee Station No' 1 l
DOCKET E: LICFJISE NOS. 50-269, CPPR-33 I
REACTOR OUTSTANDING ITD4S I,
IDENTIFIED ITEM CI,OSED
- r
- 50.
70-12, 12/1/70 ITE relays l 51.
70-12, 12/1/70 Heater and heat tracing tests
- 9..N.
52.
70-12, 12/1/70 Control rod drive cooling system tests E
53.
70-12, 12/1/70 Containment and auxiliary building vent system filters
- 54.
FSAR, Amend 25 Installation of strain gages l
U_N 12/30/70 N
55.
71-2, 1/25/71 Keowee battery room ventilation E
ff 71-2, 1/25/71 Switchyard battery blocking diode tests UN 57.
71-2, 1/25/71 Remove temporary steam line at 4 kv switchgear E
58.
71-2, 1/25/71 Controlled leak rate tests E
59.
71-2, 3/25/71 Penetration room elevator opening E
60.
71-2, 1/25/71 Verification of separation of redundant circuits UN
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'v
'l 61.
71-2, 1/25/71 Cleanup of cabh trenches vu
~
.i 62.
71-2, 1/25/71 Adequacy of leak rate tests
- i 63.
71-2, 1/25/71 Replacement of feedvater pipe cor IDEUTI dED Column: S - safety item; NC - noncompliance or nontenformance
~
item: DM - unresolvea item: IN - inquiry item; IED - Reactor Inspection and. int 6rccment Eranch reque3T; O - other source of identification (belefly specify)
Exhibit A Page 5 of 5
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