ML19317D307
| ML19317D307 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 12/17/1970 |
| From: | Brownlee V, Cuchron B, Long F US ATOMIC ENERGY COMMISSION (AEC) |
| To: | |
| Shared Package | |
| ML19317D306 | List: |
| References | |
| 50-274-70-07, 50-274-70-7, 50-287-70-07, 50-287-70-7, NUDOCS 7911270463 | |
| Download: ML19317D307 (8) | |
Text
,
~.,.
f.
1 T
U. S. ATOMIC I'IERGY CCMFSSIC.N REGION II DIVISICN OF CCMPLIANCE Report of Inspectica CO Report Nos. 50-270/70-7 50-287/70-7 Licensee:
Duke Pcwer Company Oconee 2 and 3 License Nos. CFPR-34 and 35 Category A Date of Inspection:
Nove:-Jcer 23-25, 1970 Date of Previcus Inspection:
October 26-27, 1970 Irepected By:
!. b-MW
/O- /7 - 7d V. L. Brownlee, Reactor Inspector Date (In ChargW
, /
4 f
/
U fa'
' kn ae.s
/.2 -/ 7~ $0 B. J. Ccofitan, Reactor Inspector Date Reviewed Sy:
sm
/
/t /7 2d F. J. Lcng,' SenioKeactor Inspector Dite '
Freprietary Infermation:
Ncne SCCFE An announced inspection was mads cf the two 2568 Mwt pressurized water reactors under constructicn near Seneca, Scuth Carolina, kneon as Oconee Station lics. 2 and 3 Inspecticn efforts were directed tcward a reviewof progress of constructicn, familiarization of the newly-assigned inspector, follow-cn inspection of previously-reported problems, and detemination of the scheduled onsite receiving dates for majer mechanical ec=penents.
E. J. Cochran accc=panied the inspecter fer inspecticn assistance and familiarization with the Duke organisaticnal/functientl aligrment and field operatiens prior to implementation of the inspection prcgrs: fcr the McGuire facilities.
7 911270 h 4
i A
+
C0 Rpt Ncs. 50-270/70-7 5C-287/70-7
SUMMARY
Safety Items - Ncne Nencenfonnance Items - None Status cf Previously Renorted Problems -
1.
Lcw Strencth Cenerete (Ref:
CO Rerort Mos. 50-270, 29?/70-L)
This item is considered resolved.
(Sae Section E.)
Other Sienificant Items -
1.
Results cf the Cadweld test program were reviewed.
(See Section F.)
2.
Unit No. 2 construction is estimated to be 53% complete.
(See Sections D and H.)
3 Unit No. 2 major reactor coolant loop equiptent will arrive ensite frca December 1970 through March 1971.
(See Section G.)
L.
" nit No. 3 censtruction is estimated to be 18% complete.
(See Section D.)
5.
A survey of the ensite s'torage facilities alerted the inspectcra to areas of concern for prctecticn and stcrage of ccmpcnents.
The areas were censidered isclated cases, however, and '--ad' ate corrective acckn was taker by Duke.
Clcse survai'r ce during subsequent inspections will be maintained.
(See Exhibit A, Photo Nos. 6,7,8.)
Manacement Interview - The inspectors T.et informally with the licensee representatives.
The inspectors debriefed the licensee representatives en those areas covered by the inspection and the findings.
The inspectors debrief-d fcur areas of concern.
Since the areas of criticism cculd be censidered isolated areas and quick-acticn respense by the licensee was noted, the licensee was informed that ne enfercement action was anticipated at this time.
The four areas of concern are as follows:
1.
Weld electrede bcx temperature centrol (See Section H '
i l
.m u-J C0 Ept. Nos. 50-270/7C 50-287/7C-7 1
1 1
l 2.
Tenden sheath caps (See Section H.)
3 Equipment stcrage, valves (See Section I and Exhibit A, Fheto Nos.
1 6,7,8.)
l 4.
Pipe storage (See Secti-n I. )
j The inspector requested, and the licensee ecnfimed, that main stean j
and pressurizer relief valve docuv.ents would be provided ensite fer review during the next echeduled inspection.
DETAIIS A.
Persens Ccntacted Duke Pcwer Cemrany (Duke)
{
- J. C. Rogers - Project Engineer
- J. R. Wells - Principal Field Engineer
+G. L. Hunnicutt - Senior Field Engineer T. G. Tcuchstene - Field Engineer (Civil) 4 A. B. McCrary - Supervising Technician, Cencrete j
D. L. Freeze - Field Engineer (Office)
W. E. Martin - Assistant Field Engineer (Equipment)
- D. G. Seam - Assistant Project Engineer Greenvilla Cencrete Cc rany (GCC)
P. Cross - Plant Manager E.
A 61nistratien and Cveanizatien There have been no changes in the licensee's advdnistrative organizatien'since the previous inspection, f
C.
^uality Ascurance i
Touchstone has assuned the duties of Field Engineer (Civil), replacing Hunnicutt who was preccted to Senier Field Engineer.
i
+Present at the managenent exit interview s
ed a
f
,r.,
,,,-,-.-m,. - -.,---u w
-m, y
w r-*'
CO Rpt, Nos. 5C-270/70-7
-1.-
50-287/7C-7 D.
Construction Progress 1.
Unit No. 2 Construction is estimated to be 53% complete.
Centainment deme liner welding is ccmplete.
Reactor ecolant loop components are scheduled for site arrival frem December 1970 through April 1971.
Estimated etmpletion date remaina at March 1972.
Centainment internal structures and equipment support work remain at a virtual standstill until receipt of the reactor vessel and steam generators ensite.
(See Exhibit A, Photo Ncs. 1,2,3.)
Major construction efforts were being spent in preparation for handling the reactor vessel and steam generators when they arrive.
Cenerete footings fer the gantry crane that will handle the vessels were being poured.
2.
Unit No. 1 Ccnstruction is estimated to be 18% complete.
Containment liner erection and concrete work centinue at a slow pace during installation of the large penetration areas.
Erection of centainment internal structures and equipment supports are in progress. Estinated completion date is March 1973 (See Exhibit A, Photo Nos. 2,4.)
2.
Cencrete The inspecters perfenned a folicw-on review of Duke's cencreting ;A prcgram and the results of Duke's actions to detennine and correct the causes of low strength concrete as previcusly noted (C0 Report Nes. 50-270, 287/7C-5, 70-4).
The inspectors reviewed the batch plant operations, laboratory operations and recordkeeping.
No discrepancies were cited.
Cencrete placement could not be cbserved.
The previously-ncted Icw strength concrete prcblems are to be considered resolved and no further action is anticipated.
The eencrete design mix C-2 (specified 28-day strength of 5C00 psi) was redesignated C-2T (April 21, 1970). Under advisement of H. Mitchell of GCC and R. Millhouse of Universal Atlas Cement Company (UACC), the ce;nent content was increased frcm 580 pounds per cubic yard to 600 pounds per cubic yard and the plastimite (set retarder) was increased from 12 to 13 cunces.
The field change to the design mix provided the increased strength desired.
~
- m,
4,
- 5-ea m
sn w "4m'--6*-'Whm*
NM"O
MF'
m n
i
,. m-
+
C0 Rpt. No=. 50-270/70-7 '
50.-287/70-7 A CA visit was performed at UACC, Leeds, Alabama, by Wells and Hunnicutt en May 29, 1970. Review of the cement testing records reflected that cube strengths at 28 days for the month of March had fallen below 5C00 psi and the April 28-day ette strengths were around 4e00 psi to
]
49CO psi.
The 28-day cube tests prior to March had been about 52C0 i
,si to 53C0 psi.
I Luke's conclusion is that the lcw strength concrete experienced at the site is a result of the loss of cement strength as manufactured.
l The manufacturer advised that he wculd make every effort to increase and maintain the 28-day cube strength above SCOO psi without violating his ccepany's standard of 3CCO psi (+) or (-) 150 psi at 7 days.
The company's standards exceed the ASTM requirements. Duke does not intend to reduce the C-2T mix design proportions.
Review of cencrete strength records for the C-2 and C-2T mixes were as follows:
Dates Dates Dates 01/01/70 01/01/70 04/21/70 04/17/70 05/29/70 08/31/70 Number of Cylinders 101 146 81 4
Average Strength-cf all Cylinders 5382.68 5434.21 5872.66 i
Standard Deviaticn 489.125 486.785 526.EC4 q
Coefficient of Variction 9.087%
8.9 57%
S.970%
Lowest Break 4173 kl73 L202 j
Highest Ereak 6703 6703 7056 l
Range 2510 25?O 279L 13 cylinders 19 cylinders 4 cylinders Eroke below Ercke below Brcke below l
50C0 psi 5C00 psi 5000 psi F.
Cadweld-i LA survey was made of the Cadweld records for Units 1, 2 and 3 containment i
buildings to detennine the rate of Cadweld' rejects. Unit No.1 Cadwelding is 1C0% ccmplete, No. 2 is estimated to be 50% ccmplete, and No. 3 is estirated to be 2C% complete._
i 4
l i
,~
4 CO Rpt. Mes 50-270/70-7 50-287/7C-7 Total No. of Cadwelds reviewed - 25,281.
No. Il Bar No. 16 Bar No. 18 Bar Total 4,396 12,130 9,211 No. of Tests 88 259 197 No. of Test Failures 0
1 0
No. of Visual Rejects 66 272 365 Reject Percentage
.14%
.10%
.44%
G.
Mechanical Cemtonents - Site Arrival 1.
Crane valves - 95% cnsite 2.
Velan valves (1/2 inch to 4 inches) - 95% cnsite 3
Reactor vessel - December 7,1970 4.
Steam Generator A - December 18, 1970 5
Steam Generator 3 - February 15, 1971 6.
Primary Coclant Pumps - Due testing November 23, 1970 (afg.)
The 2S-ir.ch pipe arrival is pending pump testing decision.
8.
The 36-inch pipe - April 1971 9.
Pressuriser safety valves - February 1971
- 10. Core fleed tanks - in rcute
- 11. Pressuriser - April 16, 1971
- 12. Main steam relief valves - ensite
- 13. High pressure injecticn pumps - installed
- 14. Low pressure injecticn pumps - installed
I 10 !!pt. Nos. 50-270/70-7 l 50-287/70-7
- 15. Purification demineralizer - installed
- 16. All RWDS tanks for Unit 2 - installed H.
No. 2 Unit Containment Ceme Unit No. 2 containment dome liner final closure welds were being ccepleted during the inspection.
The weather was cold, windy and was considered as marginally-acceptable weather for exposed welding.
The work area was curtained off for weather protection. The inspectors witnessed weldor cleaning, ~ grinding, welding and stemping of s, nbols for weldcr identi-ficatien.
The welding was assessed to be adequate.
The inspectors were advised that FT inspection of the completed welds would be delayed until the temperature is higher than 45"F as reccamended by the manufacturer.
Two areas of concern were noted at the.anagecent exit interview.
1.
The weld rod het box located en the deme was not at full temperature, though the thermostat was at 225*F.
The apparent problem was that heater capacity was not sufficient to maintain the set temperature due to the cold windy weather.
2.
Some vertical tendon sheaths were uncapped. Cocments to Duke QC personnel produced immediate corrective action.
(See Exhibit A, Photo No. 3.)
I.
Ecuircent Sterage The inspectors performed an inspection of the onsite-storage facilities.
Two areas of concern were noted at the management exit interview.
1.
Duke has been receiving large numbers of valves in the limited stcrage area and several instances were noted where improper protection was previded for valves placed in field stcrage.
Scme valves lacked end covers and others lacked everhead protecticn.
Cne-locatien existed where valves were located that lacked both end caps and overhead protection.
(See Exhibit A,. Photo Nos. 6,7,8.)
2.
The stainless steel storage yard was_ criticized for numerous pieces of piping that la_cked pipe end cover protection.
Cc =ents fr:c thi inspectors were accepted as legitimate -cctments and preveked i. ne< iate response frem the licensee perscnnel for ccrrective action.
Since the areas of criticism may be censidered' isolated areas and quick, corrective-acticn response by the licensee was noted, enforcement action is not anticipated.
Followup inspection efforts will be emphasiced during subsequent inspecticns.
~.
C0 Rpt. Nos. 50-270/70-7 8-
+
50-287/70-7 4
J.
Main Steam Relief. Pressurizer Relief and Electronic Evrass 1
The inspector attempted to review the purchase specification, purchase orders, and vendor quotes for the specified valves. Duke maintained no onsite records for the units. Contact was made with Duke hcme offices, Charlotte, North Carolina,- for arrangements to review the dccuments during the January inspection.
The inspector was unable to determine te what ecde "equirements the valves were to be tested.
1 K.
Documents Reviewed 1.
Specificaticn No. CS-13L-2, Specificatien for Splicing Reinforcing i
Bar using the Cadweld Prccess.
l 2.
Specification No. CS-139, Specification for Reacter Building Liner Plate and Accessory Steel.
= 3.
Specification No. 0S-139-4, Specification for Field Welding of Reactor Building Liner Plate by Manual Metal Arc Proceso.
4.
Specification No. 03-194-4, Supplemental Specification for the Erecticn and Inspection of Liner Plate.
5 Specification No. 0S-160, Specification for Concrete for the R-Reactor Building.
In additien to the above referenced specificaticns, 49 quality centrol forms, 24 quality-related forms, and 20 additional miscellanecus ferns were reviewed.
Attachments:
Exhibit A.(CO:HQ copy only) 1 i
4 1
4
+
6 4
s e
4 A
s~
b die p
aye
-4
~. -.
, _. _.